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MONTHYEARML0717905142007-06-25025 June 2007 Unit 1, Exigent Technical Specifications (TS) Change TS-461 - Modification of Restart Large Transient Testing License Condition 2. (G) 2 Project stage: Request ML0718705152007-07-0909 July 2007 Individual Notice of Consideration of Issuance of Amendments Concerning Deletion of License Condition 2 (G)2 (TAC No. MD5871) (TS-461) Project stage: Other ML0719203402007-07-16016 July 2007 Request for Additional Information for Deletion of License Condition 2.G.(2) (TAC No. MD5871) (TS-461) Project stage: RAI ML0720706672007-07-26026 July 2007 Browns, Unit 1 - Technical Specifications (TS) Change TS-461S1 - Modification of Restart Large Transient Testing License Condition 2. (G)2 - Response to Request for Additional Information (RAI) Project stage: Response to RAI ML0722506192007-08-14014 August 2007 Issuance of Amendment Deletion of License Condition 2.G.(2) TAC MD5871 Project stage: Approval ML0722602322007-08-14014 August 2007 Issuance of Amendment Deletion of License Condition 2.G.(2) TAC MD5871 Project stage: Approval 2007-07-26
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Category:Letter
MONTHYEARIR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 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 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant 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 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 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 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 ML24151A6322024-05-30030 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 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 2024-09-03
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24255A5822024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 ML24255A5802024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 - Email from Jessica Hammock to James Barstow ML24116A2012024-04-17017 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 TVAs 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 TVAs 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 TVAs Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to TVAs Request to Revised the TVA Plants Radiological Emergency Plans ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding TVAs 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 2024-09-10
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Text
July 16, 2007 Mr. William R. Campbell 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, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION FOR DELETION OF LICENSE CONDITION 2.G.(2)
(TAC NO. MD5871)(TS-461)
Dear Mr. Campbell:
By letter dated June 25, 2007, the Tennessee Valley Authority (TVA, the licensee) submitted an amendment request for Browns Ferry Nuclear Plant (BFN), Unit 1, 2 and 3, as supplemented by a letter dated July 3, 2007.
Initially, the proposed amendment would change the Unit 1 operating license to delay the performance of a large transient test at 105-percent original licensed thermal power (OLTP) required by License Condition (LC) 2.G.(2). After discussions between TVA and the U.S. Nuclear Regulatory Commission (NRC), the request was revised on July 3, 2007, to permit the deletion of LC 2.G.(2) without additional testing at 105-percent OLTP. The enclosed Request for Additional Information (RAI) is related to this submittal.
A response to the enclosed RAI is needed before the NRC staff can complete the review. This request was discussed with Mr. David Langley of your staff on July 9, 2007, and TVA agreed to respond by July 20, 2007.
If you have any questions, please contact me at (301) 415-2315.
Sincerely,
/RA/
Eva A. Brown, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
RAI cc w/enclosure: See next page
ML071920340 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA DSS/SBWB/BC DSS/SBPB/BC LPL2-2/BC NAME EBrown BClayton GCranston JWermiel for JSegala BMozafari for TBoyce DATE 07/16 /07 07/ 16 /07 07/13/07 07/16/07 07 / 16 /07 Letter to William R. Campbell from Eva A. Brown dated July 16, 2007
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION FOR DELETION OF LICENSE CONDITION 2.G.(2)
(TAC NO. MD5871)(TS-461)
DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown RidsNrrLABClayton (Hard Copy)
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REQUEST FOR ADDITIONAL INFORMATION REMOVAL OF LICENSE CONDITION 2.G.(2)
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259
- 1. Identify the acceptance criteria (both primary and secondary) applicable to the generator load reject and main steam isolation valve (MSIV) closure tests. Explain (using major system component setpoints and time requirements) how the June 23rd MSIV isolation test satisfied the acceptance criteria and how the June 9th transient provides confidence based on modeling that the acceptance criteria would be satisfied for a generator load rejection from 105-percent original licensed thermal power.
- 2. For the MSIV Closure test at 3456 Megawatt thermal (MWt) [99.9 percent rated current licensed thermal power (CLTP)], provide the following information:
a) Provide the high pressure coolant inject/reactor core isolation cooling injection water temperature; b) Provide an estimate of the fraction of decay heat from the steady state value at the time of the test, and how that differs from the assumptions in the analysis of record.
- 3. Section 14.5.2.7.1 of the Updated Final Safety Analysis Report (UFSAR) provides the analysis of an MSIV closure test at 3458 MWt (100 percent CLTP) analysis. From that analysis, provide the peak pressure calculated by ODYN and how much higher it was from the peak pressure during the test.
- 4. Additionally, Section 14.5.2.7 of the UFSAR indicated that the main steam relief valves (MSRVs) should lift momentarily during an MSIV closure. Address why the MSRVs did not lift, given that all 12 were predicted to be opened. Address the affect different initial conditions and operator action had on the observed results when compared to the expected.
William R. Campbell, Jr. BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar Decatur, AL 35609 Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Generation Development Browns Ferry Site Operations and Construction Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000 1101 Market Street Decatur, AL 35609 Chattanooga, TN 37402-2801 Mr. Larry S. Mellen Mr. Preston D. Swafford Browns Ferry Unit 1 Project Engineer Senior Vice President Division of Reactor Projects, Branch 6 Nuclear Support U.S. Nuclear Regulatory Commission Tennessee Valley Authority 61 Forsyth Street, SW.
6A Lookout Place Suite 23T85 1101 Market Street Atlanta, GA 30303-8931 Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Mr. Walter M. Justice II Corporate Nuclear Licensing Interim Vice President and Industry Affairs Nuclear Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority 4X Blue Ridge 6A Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. William D. Crouch, Manager Brian OGrady, Site Vice President Licensing and Industry Affairs Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 P.O. Box 2000 Decatur, AL 35609 Decatur, AL 35609 General Counsel Senior Resident Inspector Tennessee Valley Authority U.S. Nuclear Regulatory Commission ET 11A Browns Ferry Nuclear Plant 400 West Summit Hill Drive 10833 Shaw Road Knoxville, TN 37902 Athens, AL 35611-6970 Mr. John C. Fornicola, General Manager State Health Officer Nuclear Assurance Alabama Dept. of Public Health Tennessee Valley Authority RSA Tower - Administration 6A Lookout Place Suite 1552 1101 Market Street P.O. Box 303017 Chattanooga, TN 37402-2801 Montgomery, AL 36130-3017 Mr. Bruce Aukland, Plant Manager Chairman Browns Ferry Nuclear Plant Limestone County Commission Tennessee Valley Authority 310 West Washington Street P.O. Box 2000 Athens, AL 35611 Decatur, AL 35609 Mr. Robert H. Bryan, Jr., General Manager Mr. Masoud Bajestani, Vice President Licensing and Industry Affairs Browns Ferry Unit 1 Restart Tennessee Valley Authority Browns Ferry Nuclear Plant 4X Blue Ridge Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801