Letter Sequence RAI |
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TAC:MC3743, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MC3744, (Approved, Closed) TAC:MC3812, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
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
- Acceptance, Acceptance, Acceptance
- 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
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML041980222, ML042370100, ML050590036, ML051150191, ML051160036, ML051320148, ML051430036, ML051570381, ML051660602, ML052290397, ML060530185, ML060670304, ML060680586, ML060680590, ML060680596, ML060680599, ML060720253, ML060720272, ML060720273, ML060720281, ML060720293, ML060720295, ML060720298, ML060720303, ML060720354, ML060880464, ML060880469, ML061040217, ML061660002, ML061770163, ML061840027, ML061910705, ML062050056, ML062090482, ML062090555, ML062120411, ML062130163, ML062130343, ML062200277, ML062210102, ML062220647, ML062270240, ML062360160, ML062400472, ML062510022, ML062510371, ML062510374, ML062510382, ML062510385, ML062620064... further results
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MONTHYEARML0607202531975-05-23023 May 1975 May 23, 1975 - Final Summary Report Unit 2 Startup Project stage: Other ML0606805861975-05-23023 May 1975 May 23, 1975 - Final Summary Report Startup, Enclosure 4 Project stage: Other ML0607202721977-05-0909 May 1977 May 9, 1977 - Final Summary Report Unit 3 Startup Project stage: Other ML0606805901977-05-0909 May 1977 May 9, 1977 - Final Summary Report Startup, Enclosure 5 Project stage: Other ML0607202731992-11-30030 November 1992 a Guide for Environmental and Best Management Practices for Tennessee Valley Authority Transmission Construction and Maintenance Activities Project stage: Other ML0607202982001-03-13013 March 2001 Environmental Assessment Bear Creek Reservoirs Land Management Plan Project stage: Other ML0607202952001-03-31031 March 2001 Bear Creek Reservoirs Land Management Plan, Resource Stewardship Bear Creek Watershed Project stage: Other ML0606805992001-03-31031 March 2001 Bear Creek Reservoirs Land Management Plan Project stage: Other ML0419802222004-07-0909 July 2004 Technical Specification 436 - Increased Main Steam Isolation Valve Leakage Rate Limits and Exemption from 10CFR50, Appendix J Project stage: Other ML0423701002004-08-23023 August 2004 Browns Ferry, Ltr, Framatome Proprietary Review Project stage: Other ML0423708492004-08-23023 August 2004 (BFN) - Unit 1- Proposed Technical, Specifications (TS) Change TS - 431 - Request for License Amendment - Extended Power Uprate (EPU) Operation Probabilistic Safety Assessment (PSA) Update Project stage: Request ML0429202832004-11-18018 November 2004 Ltr, Results of Acceptance Review for Extended Power Uprate Project stage: Acceptance Review ML0431004762004-11-18018 November 2004 Ltr, Results of Acceptance Review for EPU Project stage: Acceptance Review ML0433701792004-12-29029 December 2004 RAI Re Extended Power Uprate Project stage: RAI ML0434400452004-12-30030 December 2004 RAI, Extended Power Uprate Project stage: RAI ML0500303612005-01-0606 January 2005 Ltr, Request for Information for Status of Amendment (Tac No. MC1330, MC1427, MC2305, MC3812, MC4070, MC4071, MC4072, MC4161, MC3743, MC3744) Project stage: RAI ML0505900362005-02-16016 February 2005 Enclosure 2, 02/01/2005 Conference Call with TVA Presentation Slides on TS Changes Using Method 3 for Interim Solution Project stage: Other ML0505601502005-02-23023 February 2005 Response to NRC Acceptance Review Letter and Request for Additional Information Related to Technical Specifications Change No. TS-431 - Request for Extended Power Uprate Operation Project stage: Request ML0505603372005-02-23023 February 2005 (BFN) - Response to Nrc'S Acceptance Review Letter and Request for Additional Information Related to Technical Specifications Change No. TS-418 - Request for Extended Power Uprate Operation (Tac Nos MC3743 and MC3744) Project stage: Request ML0607202932005-02-28028 February 2005 Hydrothermal Modeling of Browns Ferry Nuclear Plant with Units 1, 2, and 3 at Extended Power Uprate Project stage: Other ML0606805962005-02-28028 February 2005 Hydrothermal Modeling of Browns Ferry with Units 1, 2, and 3 at Extended Power Uprate Project stage: Other ML0511501912005-04-19019 April 2005 Enclosure 3, Ltr, Licensing Action Status and Interdependencies Project stage: Other ML0511702442005-04-25025 April 2005 (BFN) - Unit 1 - Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS-431 - Request for Extended Power Uprate Operation Project stage: Request ML0511702422005-04-25025 April 2005 (BFN) - Units 2, and 3 - Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS-418 - Request for Extended Power Uprate Operation Project stage: Request ML0514300362005-05-20020 May 2005 Response to Nrc'S Letter on Licensing Action Status and Interdependencies, Project stage: Other ML0513201462005-05-27027 May 2005 EPU Acceptance Review Results to Increase Maximum Authorized Power Level (TAC No. MC3743, MC3744) (TS-418) Project stage: Acceptance Review ML0515802492005-06-0606 June 2005 Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS - 431 - Request for License Amendment Extended Power Uprate (EPU) Operation Project stage: Request ML0516403912005-06-0606 June 2005 Response to Technical Specifications (TS) Change No. TS-418 - Request for License Amendment - Extended Power Uprate (EPU) Operation Project stage: Request ML0517902372005-06-24024 June 2005 Part 21 Notification - Critical Power Determination for G314 and GE12 Fuel with Zircaloy Spacers, 06/24/2005 Project stage: Request ML0513201482005-06-29029 June 2005 Ltr., Ind FRN Facility Operating License for EPU and Opportunity for a Hearing Project stage: Other ML0515703812005-06-29029 June 2005 Fanp, Withholding Information from Public (TACs MC3743, MC3744) Project stage: Other ML0516606022005-06-29029 June 2005 Ltr., Withholding Public Disclosure for GE Company (TACs MC3743, MC3744) Project stage: Other ML0511600362005-07-0101 July 2005 Notice of Consideration of Issuance of Amendment and Notice of Opportunity for a Hearing Regarding Extended Power Uprate (Tac No. MC3743, MC3744) Project stage: Other ML0518703902005-07-0707 July 2005 06/08/05, Meeting Summary with TVA and Framatome Regarding Fuel Analysis Methodology, Enclosure 2, Framatome Presentation Project stage: Meeting ML0520706042005-07-26026 July 2005 Notice of Meeting with Tennessee Valley Authority (TVA) BFN Units 1, 2, and 3, and Sequoyah Units 1 and 2 on Resolution of Instrument Setpoint Concerns Project stage: Meeting ML0524204912005-08-23023 August 2005 Ltr., GE Request for Withholding Information from Public on Steam Dryer Analysis for EPU Conditions Project stage: Withholding Request Acceptance ML0522901442005-09-0202 September 2005 Summary of Meeting with the Tennessee Valley Authority Regarding Plant-Specific Resolution of Instrument Setpoint Concerns Project stage: Meeting ML0522903972005-09-0202 September 2005 TVA Handout Method 3 Issue BFN Proposed Resolution Project stage: Other ML0524303412005-10-0303 October 2005 RAI, Extended Power Uprate (TS-431) (Tac No. MC3812) Project stage: RAI ML0525104462005-10-0303 October 2005 Request for Additional Information Regarding Extended Power Uprate Project stage: RAI ML0535601862005-12-19019 December 2005 Response to NRC Round 2 Request for Additional Information Related to Technical Specifications Change No. TS-418-Request for Extended Power Uprate Operation Project stage: Request ML0535601942005-12-19019 December 2005 Response to NRC Round 2 Requests for Additional Information Related to Technical Specifications Change No. TS-431 - Request for Extended Power Uprate Operation Project stage: Request ML0535601202005-12-22022 December 2005 Request for Additional Information, Information Concerning Extended Power Uprate Project stage: RAI ML0535601772005-12-22022 December 2005 Request for Additional Information, Concerning Extended Power Uprate Project stage: RAI ML0535703412006-01-19019 January 2006 Revised Schedule for Response to Extended Power Uprate Requests for Additional Information Project stage: RAI ML0614502612006-02-0101 February 2006 Response to NRC Request EMEB-B.6 from NRC Round 2 Requests for Additional Information Related to Technical Specification (TS) Change No. TS-431- Request for Extended Power Uprate. Project stage: Request ML0603207332006-02-0101 February 2006 Response to NRC Request EMEB-B.7 from NRC Round 2 Requests for Additional Information Related to Technical Specification (TS) Change No. TS-418 - Request for Extended Power Uprate Project stage: Request ML0603901352006-02-0808 February 2006 Forthcoming Meeting with Tennessee Valley Authority, to Discuss Various Topics Regarding Tva'S Extended Power Uprate Amendment Request for the Browns Ferry Nuclear Plant, Units 1 and 2 and 3 Project stage: Meeting ML0607202812006-02-28028 February 2006 NEDO-33173, Applicability of GE Methods to Expanded Operating Domains. Project stage: Other ML0606203072006-02-28028 February 2006 Technical Specifications Change TS-418 - Response to Request for Additional Information SPSB-A.11 Regarding Extended Power Uprate - Credit for Net Positive Suction Head Project stage: Response to RAI 2005-02-28
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Category:Letter
MONTHYEARIR 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) 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) 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 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 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) ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 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 CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24106A2432024-04-16016 April 2024 Letter to Federally Recognized Tribes-Ben, Mississippi Band of Choctaw Indians ML24106A2512024-04-16016 April 2024 Letter to Federally Recognized Tribes-Morrow, Thlopthlocco Tribal Town ML24106A2632024-04-16016 April 2024 Ltr to State Recognized Tribes-Hamilton, Cher-O-Creek Intra Tribal Indians ML24106A2462024-04-16016 April 2024 Letter to Federally Recognized Tribes-Cypress, Miccosukee Tribe ML24107A0032024-04-16016 April 2024 Letter to Federally Recognized Tribes-Pierite, Tunica-Biloxi Tribe of Louisiana ML24106A2592024-04-16016 April 2024 Ltr to State Recognized Tribes-Bridges, United Cherokee Aniynwiya ML24106A2452024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Cernek, Couchatta Tribe of Louisiana ML24106A2622024-04-16016 April 2024 Ltr to State Recognized Tribes-Gilmore, Southeastern Mvskoke Nation ML24106A2472024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Hicks, Eastern Band of Cherokee Indians ML24106A2542024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Rogers, Jena Band of Choctaw Indians ML24106A2652024-04-16016 April 2024 Letter to State Recognized Tribes-Wright, Ma-Chis Lower Creek Indian Tribe of Alabama ML24102A0422024-04-16016 April 2024 Ltr to State Recognized Tribes-Russell, Cherokee Tribe of Northeast Alabama ML24106A2482024-04-16016 April 2024 Letter to Federally Recognized Tribes-Hill, Muscogee (Creek) Nation ML24102A0412024-04-16016 April 2024 Ltr to SHPO-Request for Scoping Comments Concerning the Env Review of the Browns Ferry Subsequent License Renew App ML24106A2382024-04-16016 April 2024 Letter to Federally Recognized Tribes-Anoatubby, Chickasaw Nation ML24106A2572024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Yahola, Kialegee Tribal Town ML24106A2562024-04-16016 April 2024 Letter to Federally Recognized Tribes-Wallace, Eastern Shawnee Tribe of Oklahoma ML24107A0022024-04-16016 April 2024 Letter to Federally Recognized Tribes-Bunch, United Keetoowah Band of Cherokee Indians ML24106A2492024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Hoskin, Jr., Cherokee Nation ML24106A2412024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Battise, Alabama-Coushatta Tribe of Texas ML24106A2402024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Barnes, Shawnee Tribe 2024-08-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A0272024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) ML21173A1042021-06-21021 June 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to TS 3.8.6 ML21041A5422021-02-10010 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt 10 CFR 50.69 ML21041A5432021-02-0505 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Draft Request for Additional Information Regarding 10 CFR 50.69 LAR ML21026A1652021-01-26026 January 2021 Document Request for Browns Ferry Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-02 ML20297A3012020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt TSTF-425 ML20296A3782020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Incorporate TMRE ML20294A3762020-09-23023 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Adopt TSTF-425 ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information ML20224A4732020-08-11011 August 2020 Requalification Program Inspection Browns Ferry Nuclear ML20195B1302020-07-13013 July 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Alternative Request No. 0-ISI-47 ML20149K3212020-05-27027 May 2020 RP Inspection Document Request, Browns Ferry 2020-003 ML20254A3032020-05-13013 May 2020 Request for Supporting Information for the Browns Ferry, Units 1, 2, and 3 Seismic Probabilistic Risk Assessment Audit Review ML20054B8592020-02-20020 February 2020 Emergency Preparedness Program Inspection Request for Information ML20014E6552020-01-14014 January 2020 01 RP Inspection Document Request ML19196A0752019-07-12012 July 2019 NRR E-mail Capture - Final RAIs Browns Ferry Nuclear, Units 1, 2, 3 - Application to Revise Technical Specifications to Adopt TSTF-542 Revision 2, Reactor Pressure Vessel Water Inventory Control ML19116A0712019-06-0303 June 2019 Request for Additional Information Related Resubmittal of Proposed Alternative Request No. 1-ISI-27 for the Period of Extended Operation ML18331A5442018-12-0606 December 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - (Non-Proprietary) ML18317A1642018-11-20020 November 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - Non-Proprietary ML18263A1412018-09-11011 September 2018 NRR E-mail Capture - Browns Ferry Unit 1: RAI Associated with Relief Request 1-ISI-28 ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18108A1872018-04-18018 April 2018 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000259/2018411, 05000260/2018411, and 05000296/2018411 ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17216A0062017-08-18018 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to LAR to Revise Modifications and Implementations Related to NFPA 805 for Fire Protection for Light Water Reactor Generating Plants (CAC Nos. MF9814-MF9816) ML17163A0502017-06-0808 June 2017 NRR E-mail Capture - RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257 ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML16288A0182016-10-27027 October 2016 Browns Ferry Nuclear Plant, Units 2 and 3 - RAI Related to Relief Request for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI Requirements (CAC Nos. MF7795 and MF7796) ML16236A0732016-08-31031 August 2016 Request for Additional Information Related to License Amendment Request to Add New Technical Specification 3.3.8.3 ML16203A0272016-07-25025 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (CAC Nos. MF6738, MF6739, and MF6740) ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16187A2932016-07-21021 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743) ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16146A6352016-06-13013 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16145A1582016-06-0303 June 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (SBPB-RAI 4) (CAC Nos. MF6741, MF6742, and MF6743) 2024-04-17
[Table view] |
Text
September 27, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 10 (TS-431 AND TS-418) (TAC NO. MC3812, MC3743 AND MC3744)
Dear Mr. Singer:
By letters dated June 28 and 25, 2004, the Tennessee Valley Authority (TVA, the licensee) submitted amendment requests for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, as supplemented by letters dated August 23, 2004, February 23, April 25, June 6, and December 19, 2005, February 1 and 28, March 7, 9, 23, and 31, April 13, May 5 and 11, June 12, 15, 23 and 27, and July 6, 21, 24, 26, and 31, and August 4, 16, and 18, and September 1 and 15, 2006.
The proposed amendments would change the BFN operating licenses to increase the maximum authorized power level by approximately 20 percent above the current maximum authorized power level for Unit 1, and approximately 15 percent for Units 2 and 3. The proposed amendments would also change the Unit 1 licensing bases and associated Technical Specifications to credit 3 pounds per square inch gauge (psig) for containment accident pressure following a loss-of-coolant accident and increase the reactor steam dome pressure by 30 psig. The proposed amendments would also change the Units 2 and 3 licensing bases to revise the credit for containment accident pressure from 3 pounds for short-term and 1 pound for long-term, to 3 pounds for the duration of a loss-of-coolant accident, and revise the maximum ultimate heat sink temperature.
K. Singer A response to the enclosed Request for Additional Information is needed before the Nuclear Regulatory Commission staff can complete the review. These requests were provided in draft form to your staff by e-mail September 22, 2006. A response is requested by October 4, 2006.
If you have any questions, please contact me at (301) 415-2315.
Sincerely,
/RA/
Eva A. Brown, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Request for Additional Information cc w/enclosure: See next page
ML062690560 NRR-088 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/PM LPL2-2/LA EEMB/BC NAME LRegner EBrown MChernoff BClayton KManoly by memo DATE 9/27/06 9/27/06 9/27/06 9/27/07 8/17/06 APLA/BC DSS/SCVB DSS/SBWB LPL2-2/BC MRubin TMartin TMartin LRaghavan by memo by memo by memo 8/31/06 8/22/06 9/14/06 9/27/06 REQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 DOCKET NOS. 50-259, 50-260, 50-296 EEMB 115/85. The Nuclear Regulatory Commission (NRC) staff requested a discussion of any weld reinforcement following fatigue cracking of drain channel in the BFN steam dryers. In its response to this request (identified as EEMB.C.1 on page E1-106 of the July 26 submittal), the Tennessee Valley Authority (TVA, the licensee) states it has periodically inspected the Units 2 and 3 repaired drain channel welds subsequent to 105 percent original licensed thermal power (OLTP) operation.
- a. Identify the inspection technique used for Units 2 and 3 and explain whether that technique was qualified to detect fatigue cracks.
- b. Specify whether these periodic inspections will be performed subsequent to 105 percent OLTP operation for Unit 1. If so, identify the inspection technique to be used and explain whether that technique is qualified to detect fatigue cracks.
116/86. The NRC staff requested a discussion of the post-modification inspection procedures for the BFN steam dryer modifications. In its response to this request (identified as EEMB.C.19 on pages E1-125 and 126 of the July 26 submittal), TVA stated that the post-modification inspection will be conducted employing visual inspection (VT-2). Discuss the adequacy of this inspection method, and the ability to conduct a more detailed inspection of the BFN Unit 1 steam dryer.
117/87. Section 9.9 of Rev. 2 of the steam dryer stress report states that TVA plans to use pressure transducers mounted in holes in the main steam lines (MSLs) to measure fluctuating pressures as input to the acoustic circuit model (ACM).
Provide a schematic of the proposed installation, which shows clearly the location of the pressure transducer with respect to the inner surface of the MSL walls. Since pressure transducers exposed to steam flow will measure acoustic pressure and turbulence traveling through the MSLs and over the pressure transducer, quantify any bias error or uncertainty that might be introduced to the dryer leads computed with the Bounding Pressure ACM by the presence of turbulence-induced pressures in the ACM inputs.
Enclosure
118. In the July 26, 2006, response, the licensee indicated that Unit 1 is currently performing restart modifications and that the final stress analysis results, which reflect the as-built configuration, are not available for most of the reactor coolant pressure boundary and balance-of-plant systems. Provide the schedule for completion of the piping system evaluation for Unit 1. Upon completion, provide the evaluation summary for piping systems and their supports including main steam, feedwater, recirculation, residual heat removal, and torus-attached piping systems. The information should include the calculated maximum stresses and fatigue usage factors, as necessary, for piping systems and their supports similar to those provided for the Units 2 and 3 extended power uprate (EPU) evaluation.
APLA 27/29. For this request, an operator action is important to risk if any one of the following criteria is met: (1) Fussell Vesely (FV) importance to core damage frequency (CDF) greater than 0.005; (2) FV importance to large early release frequency (LERF) greater than 0.005; (3) risk achievement worth (RAW) importance to CDF greater than two; or (4) RAW importance to LERF greater than two. Provide the following information for operator actions modeled in the probabilistic risk assessment that are important to risk:
- a. Basic event (operator action) name
- b. Description
- c. Where action is performed (e.g., control room, outside control room, both)
- d. For the pre-EPU model;
- i. FV importance to CDF ii. RAW importance to CDF iii. FV importance to LERF iv. RAW importance to LERF
- v. time available to the operator from receipt of the appropriate cue until the action must be complete for successful mitigation of core damage or large early release vi. Human error probability
- e. For the post-EPU model:
- i. FV importance to CDF ii. RAW importance to CDF iii. FV importance to LERF iv. RAW importance to LERF
- v. Time available to the operator from receipt of the appropriate cue until the action must be complete for successful mitigation of core damage or large early release
vi. Human error probability ACVB 68/66. The staff has determined that the information in the May 24, 1976, report may not be sufficient to justify credit for a value of required net positive suction head (NPSH) less than the 3 percent head loss value.
- a. Provide any supporting information not included in the May 24, 1976, report that supports the use of a lower value such as:
- i. accelerometer data, ii. time that the Residual Heat Removal (RHR) pump was in cavitation, and iii. the inspections performed on the pump before and after testing.
- b. Describe the operational history of RHR pump 3A. Address whether pump RHR 3A experienced any abnormal operation since this testing.
69/67. Describe the peak short-term loss-of-coolant accident (LOCA) suppression pool temperature at 105 percent power. Provide the service water temperature assumed in this analysis.
70/68. Verify that at 105 percent power, for the short-term LOCA, the available NPSH is always greater than the required NPSH at the peak RHR pump flow (11,500 gpm) without reliance on the testing reported in the May 24, 1976, report.
SBWB 50/75. Provide the sequence of events tables for the limiting Appendix K Large Break LOCA and the limiting Appendix K Small Break LOCA (0.06 ft2) discharge break with a battery failure and only five automatic depressurization system (ADS) valves actuated. The staff also requests the licensee to provide the low pressure core spray and low pressure coolant injection head versus flow curve, limiting axial power shape, and ADS relief valve set pressure and relief capacity used in the analysis.
Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW.
Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Mr. Glenn W. Morris, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Robert J. Beecken, Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, Manager 10833 Shaw Road Nuclear Assurance and Licensing Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609