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Results
Other: ML040650206, ML040910016, ML041310029, ML042240255, ML042990519, ML051180464, ML051250308, ML060410288, ML060450582, ML060950060, ML061110094, ML061110102, ML061110126, ML061140322, ML061730464, ML091870509, ML11171A037, ML11171A038, ML11308A018
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MONTHYEARML0400603592003-12-31031 December 2003 Letter Transmitting Browns Ferry, Units 1, 2 and 3, Application for Renewed Operating Licenses Project stage: Request ML0406502062004-03-0404 March 2004 Determination of Acceptability and Sufficiency for Docketing and Opportunity for a Hearing Regarding the Application from Tennesssee Valley Authority for Renewal of the Operating Licenses for Browns Ferry, Units 1, 2 & 3 Project stage: Other ML0409100162004-03-31031 March 2004 Review Schedule for Application for Renewal of the Operating Licenses for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Other ML0413100292004-05-0606 May 2004 & 03/31/2004 Summary of Telephone Conferences with Tennesssee Valley Authority Concerning Activities on Browns Ferry Nuclear Plant, Units 1, 2 & 3 LRA Project stage: Other ML0419501002004-06-10010 June 2004 Audit and Review Plan for Plant Aging Management Programs and Reviews - Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Request ML0418101682004-06-28028 June 2004 Summary of Telephone Conference on May 27, 2004, Between the U.S. NRC and the Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 and 3 LRA Project stage: Draft RAI ML0421104852004-07-28028 July 2004 Summary of Telephone Conference Held on July 1, 2004, Between NRC and TVA Concerning Draft Requests for Additional Information (D-RAI) on Browns Ferry Nuclear Plant Units 1, 2,& 3 Project stage: Draft RAI ML0422402552004-08-10010 August 2004 Audit and Review Plan for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plants, Units 1, 2 and 3 Project stage: Other ML0424005502004-08-26026 August 2004 Summary of Telephone Conference Held on July 27, 2004, Between U.S. Nuclear Regulatory Commission & Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 & 3, License Renew Project stage: Draft RAI ML0424502112004-08-31031 August 2004 Summary of Telephone Conference Held on July 12, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) and the Tennessee Valley Authority (TVA) Concerning Requests for Additional Information (RAI) on Browns Ferry Nuclear Plant, Unts 1, Project stage: RAI ML0426005222004-09-16016 September 2004 Summary of Telephone Conference Held on August 19, 2004, Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 & 3 LR Project stage: Draft RAI ML0429905192004-10-21021 October 2004 Summary of Telephone Conference Held on September 22, 2004, Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority Concerning Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA Project stage: Other ML0430905772004-11-0404 November 2004 Request for Additional Information for the Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA (TAC Nos. MC1704, MC1705 and MC1706.) Project stage: RAI ML0430905732004-11-0404 November 2004 Request for Additional Information for the Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA Project stage: RAI ML0511804642005-04-26026 April 2005 Audit and Review Report for Plant Aging Management Programs (Amps) and Aging Management Reviews (Amrs), Browns Ferry Nuclear Plant, Untis 1, 2 and 3 and Memo Project stage: Other ML0512503082005-05-0404 May 2005 Memo, Audit and Review Report for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plant Project stage: Other ML0535603282005-12-20020 December 2005 License Renewal Application - Supplemental Information for the Time Limited Aging Analysis for Stress Relaxation of the Core Plate Hold-Down Bolts and the Unit 1 Periodic Inspection Program (TAC Nos. MC1704. Project stage: Supplement ML0601204532006-01-12012 January 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Tac Nos. MC1704, MC1705, MC1706) Project stage: Approval ML0601103412006-01-12012 January 2006 Transmittal Letter to K. Singer: Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Approval ML0604102882006-01-31031 January 2006 License Renewal Application (LRA) - Annual Update Project stage: Other ML0603302952006-01-31031 January 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1,2, and 3 (TAC Nos. MC1704, MC1705, and MC1706) - Request for Additional Information Related to Appendix F Items in the Application Project stage: Approval ML0604505822006-02-14014 February 2006 License Renewal Application (LRA) - Revised Commitment Tables Project stage: Other ML0606203532006-03-0303 March 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Request for Additional Information Related to Appendix F Items in the Application and the Topics Discussed in the Public Meeting... Project stage: Approval ML0606603742006-03-0707 March 2006 (BFN) Units 1, 2, and 3 License Renewal Application (LRA) - Supplemental Information for the Unit 1 Periodic Inspection (TAC MC1704, MC1705 and MC1706) Project stage: Supplement ML0607903762006-03-0707 March 2006 License Renewal Application (LRA) - Supplemental Information for Open Item 2.4-3 Project stage: Supplement ML0609500602006-04-0404 April 2006 (BFN) - Units 1, 2, and 3 License Renewal Application (LRA) - Unit 1 Lower Drywell Liner Inspections, Unit 1 Periodic Inspection Program, and Residual Heat Removal Service Water Piping Inspections Project stage: Other ML0609701682006-04-21021 April 2006 Transmittal of Supplement 1 to the Safety Evaluation Report (NUREG-1843) - Supplemental Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MC1704, MC1705, MC1706) Project stage: Approval ML0611403222006-04-21021 April 2006 Brown Ferry Units 1, 2, and 3 - License Renewal Application - Revised Commitment List Project stage: Other ML0611401822006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 3 Project stage: Acceptance Review ML0611403522006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 1 Project stage: Acceptance Review ML0609703322006-05-0404 May 2006 Ltr to Karl W. Singer - Issuance of Renewed Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Approval ML0611101022006-05-0404 May 2006 Renewed Facility Operating License DPR-52 Project stage: Other ML0611101262006-05-0404 May 2006 Renewed Facility Operating License No. DPR-68 Project stage: Other ML0611100942006-05-0404 May 2006 Renewed Facility Operating License DPR-33 Project stage: Other ML0611402092006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 2 Project stage: Acceptance Review ML0609703552006-05-0404 May 2006 Federal Register Notice - Notice of Issuance of Renewed Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 for an Additional 20-year Period Project stage: Approval ML0613600442006-06-0707 June 2006 Agenda for Public Meeting with Entergy Operations Incorporated Regarding Spent Fuel Pool Rack Configuration Changes at ANO-1 and ANO-2 on Wednesday 06/07/2006, TAC Nos. MC1704, MC1705 Project stage: Meeting ML0617304642006-06-22022 June 2006 Corrections to Technical Specifications and Renewed Facility Operating License No. DPR-33, for Unit 1 Project stage: Other ML0619102062006-07-0606 July 2006 03/01/2006 - Summary of Meeting with TVA on the License Renewal Application for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Meeting ML0618803982006-07-0606 July 2006 03/09/2006 Summary of a Meeting Held Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority on the License Renewal Application for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Meeting ML0918705092009-07-17017 July 2009 G20090346/LTR-09-0303/EDATS: SECY-2009-0304 - Ltr. Mario Bonaca Report on the Safety Aspects of the License Renewal Application for the National Bureau of Standards Test Reactor Project stage: Other ML11171A0382010-12-31031 December 2010 NEDO-33632, Rev. 0, Browns Ferry (Units 1-3), Core Plate Bolt Analysis Stress Analysis Report. Project stage: Other ML11171A0372011-06-15015 June 2011 BWRVIP-25 Core Plate Bolt Stress Analysis Project stage: Other ML11308A0182011-11-0101 November 2011 One-Time Inspection Procedure, 0-TI-565, Rev. 0003 Project stage: Other 2005-05-04
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Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24043A0462024-02-16016 February 2024 Summary of Meeting with TVA to Discuss Use of Risk-Informed Process Evaluation (RIPE) for a Proposed LAR Regarding Elimination of Limiting Condition for Operation Actions for Rod Worth Minimizers ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23116A2472023-05-23023 May 2023 Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control ML23101A1102023-05-16016 May 2023 Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications ML23073A2902023-05-0202 May 2023 Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22327A0182022-12-0101 December 2022 Correction of Error Incurred During Issuance of License Amendment No. 322 ML22273A1032022-11-22022 November 2022 Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification ML22220A2602022-11-21021 November 2022 Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A ML22138A3252022-06-24024 June 2022 Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis ML22020A2282022-03-16016 March 2022 Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2 ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21173A1772021-07-27027 July 2021 Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20190A1052020-08-11011 August 2020 Correction to Amendment No. 319 Regarding Revisions to Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times ML19294A0112019-12-26026 December 2019 Issuance of Amendment Nos. 311, 334, and 294 Adopt Technical Specifications Task Force Traveler, TSTF-542, Revision 2 ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19198A0012019-08-13013 August 2019 Issuance of Amendment Nos. 308, 331, and 291 to Extend Implementation Due Date for Modifications 102 and 106 Related to NFPA 805 (Eid L-2019-LLA-0140) ML19037A1372019-04-0202 April 2019 Revisions to Modifications 85, 102 and 106 Related to National Fire Protection Association 805 Performance-based Standard for Fire Protection of Light Water Reactor Electric Generating Plants ML18241A3192018-10-0909 October 2018 Issuance of Amendment Nos. 306, 329, and 289 to Revise Approved NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants-Revision ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) ML18138A4522018-05-29029 May 2018 Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20 ML17289A0322017-12-22022 December 2017 Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160) ML17215A2432017-10-0202 October 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566) ML17032A1202017-08-14014 August 2017 Non-Proprietary Issuance of Amendments Regarding Extended Power Uprate ML17034A3602017-03-27027 March 2017 Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ... ML17052A1362017-03-16016 March 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendment Nos. 297, 321, and 281 to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 (CAC Nos. MF8125, MF8126, and MF8127) ML16330A1582017-01-17017 January 2017 Issuance of Amendments Regarding Revisions to Technical Specification 4.3.1.2, Fuel Storage Criticality ML16028A4142016-04-26026 April 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15317A4782016-02-0909 February 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15344A3212016-01-0707 January 2016 Issuance of Amendment Regarding Modification of Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits ML15321A4722015-12-23023 December 2015 Issuance of Amendments Regarding Revision to Table 3.3.6.1-1, Primary Containment Isolation Instrumentation ML15287A2132015-12-16016 December 2015 Issuance of Amendments Regarding Technical Specification Changes to Reactor Core Safety Limits ML15324A2472015-12-14014 December 2015 Issuance of Amendment to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Valves to Licensee Control ML15287A3712015-12-0404 December 2015 Issuance of Amendments for the Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-535 (CNL-15-029) ML15212A7962015-10-28028 October 2015 Issuance of Amendments to Transition to Fire Protection Program NFPA-805 ML15251A5402015-09-29029 September 2015 Issuance of Amendment Regarding Control Rod Scram Time Testing Frequency Per TSTF-460, Revision 0 ML15065A0492015-06-0202 June 2015 Issuance of Amendment Revising Pressure and Temperature Limit Curves ML13254A0812013-09-13013 September 2013 Issuance of Amendment Under Exigent Circumstances to Remove Notes from Technical Specifications 3.4.9-1 and 3.4.9-2 2024-02-16
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TENNESSEE VALLEY AUTHORITYDOCKET NO. 50-296BROWNS FERRY NUCLEAR PLANT, UNIT 3RENEWED FACILITY OPERATING LICENSERenewed License No. DPR-681.The Nuclear Regulatory Commission (NRC or the Commission), having previously madethe findings set forth in License DPR-68 issued on July 2, 1976, has now found that:A.The application for license filed by the Tennessee Valley Authority (TVA or thelicensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made;B. Construction of the Browns Ferry Nuclear Plant, Unit 3 (the facility) has beensubstantially completed in conformity with Construction Permit No. CPPR-48 and the application, as amended, the provisions of the Act and the rules andregulations of the Commission;C.Actions have been identified and have been or will be taken with respect to(1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1); and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by the renewed operatinglicense will continue to be conducted in accordance with the current licensingbasis, as defined in 10 CFR 54.3, for the facility, and that any changes made tothe facility's current licensing basis in order to comply with 10 CFR 54.29(a) are in accordance with the Act and the Commission's regulations;D. The facility will operate in conformity with the application, as amended, theprovisions of the Act, and the rules and regulations of the Commission;E. There is reasonable assurance: (i) that the activities authorized by the renewedoperating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with therules and regulations of the Commission;F. The licensee is technically and financially qualified to engage in the activitiesauthorized by this renewed operating license in accordance with the rules and regulations of the Commission;G. The licensee has satisfied the applicable provisions of 10 CFR Part 140,"Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; Renewed License No. DPR-68H. The issuance of this renewed operating license will not be inimical to thecommon defense and security or to the health and safety of the public;I. The staff, after weighing the environmental, economic, technical and otherbenefits of the facility against environmental costs, and considering availablealternatives, has found that the adverse environmental impacts of license renewal are not so great that preserving the option of license renewal would beunreasonable, the issuance of Renewed Facility Operating License No. DPR-68,subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 51 (formerly Appendix D to Part 50), of the Commission's regulations and all applicable requirements have been satisfied; andJ. The receipt, possession, and use of source, byproduct and special nuclearmaterial as authorized by this renewed license will be in accordance with theCommission's regulations in 10 CFR Parts 30, 40, and 70, including 10 CFR Sections 30.33, 40.32, 70.23, and 70.31.2.The Atomic Safety and Licensing Board having dismissed the proceeding relating to thelicensing action in a "Memorandum and Order," dated November 27, 1973, is superseded by Renewed Facility Operating License No. DPR-68 which is hereby issuedto read as follows:A. This renewed license applies to the Browns Ferry Nuclear Plant, Unit 3, a boilingwater nuclear reactor and associated equipment (the facility), owned by the TVA.The facility is located in Limestone County, Alabama, and is described in the"Final Safety Analysis Report" (Amendment 9) as supplemented and amended (Amendments 10 through 65), the licensee's Draft Environmental Statement andsupplement thereto dated July 1971, and November 8, 1971, respectively, andthe licensee's Final Environmental Statement dated September 1, 1972.B. Subject to the conditions and requirements incorporated herein, the Commissionhereby licenses Tennessee Valley Authority:(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing ofProduction and Utilization Facilities," to possess, use, and operate thefacility at the designated location in Limestone County, Alabama, inaccordance with the procedures and limitations set forth in this renewed license;(2) Pursuant to the Act and 10 CFR Parts and 70, to receive, possess,and use at any time source and special nuclear material as reactor fuel in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report as supplemented and amended; Renewed License No. DPR-68(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive,possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive,possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components;(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but notseparate, such byproduct and special nuclear materials as may be produced by the operation of the facility.C. This renewed operating license shall be deemed to contain and is subject to theconditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:(1) Maximum Power LevelThe licensee is authorized to operate the facility at steady state reactorcore power levels not in excess of 3458 megawatts thermal.(2) Technical SpecificationsThe Technical Specifications contained in Appendices A and B, asrevised through Amendment No.
,are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.For Surveillance Requirements (SRs) that are new in Amendment toFacility Operating License DPR-68, the first performance is due at theend of the first surveillance interval that begins at implementation of the Amendment 212. For SRs that existed prior to Amendment
,including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date thesurveillance was last performed prior to implementation of Amendment 212. Renewed License No. DPR-68(3) The licensee is authorized to relocate certain requirements included inAppendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's application dated September 6, 1996; as supplementedMay 1, August 14, November 5 and 14, December 3, 4, 11, 22, 23, 29, and 30, 1997; January 23, March 12, April 16, 20 and 28, May 7, 14, 19,and 27, and June 2, 5, 10 and 19, 1998; evaluated in the NRC staff'sSafety Evaluation enclosed with this amendment. This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment.(4) Deleted.
(5) Classroom and simulator training on all power uprate related changes thataffect operator performance will be conducted prior to operating at upratedconditions. Simulator changes that are consistent with power uprate conditions will be made and simulator fidelity will be validated inaccordance with ANSI/ANS 3.5-1985. Training and the plant simulator willbe modified, as necessary, to incorporate changes identified during startup testing. This amendment is effective immediately.(6) The licensee shall fully implement and maintain in effect all provisions ofthe Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Browns Ferry Nuclear Plant Physical Security Plan, Training and Qualification Plan, and Contingency Plan," submitted by letter datedSeptember 10, 2004, and supplemented on October 22, 2004.(7) Browns Ferry Nuclear Plant shall implement and maintain in effect allprovisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the safety evaluations dated December 8, 1988; March 6, 1991, March 31, 1993; November 2, 1995; and Supplement dated November 3, 1989; subject to the following provision:The licensee may make changes to the approved fire protectionprogram without prior approval of the Commission only if those changes would not adversely affect the ability to achieve andmaintain safe shutdown in the event of a fire.(8)Deleted. Renewed License No. DPR-68(9)The licensee shall maintain the Augmented Quality Program for theStandby Liquid Control System to provide quality control elements to ensure component reliability for the required alternative source termfunction defined in the Updated Final Safety Analyses Report (UFSAR).D.The UFSAR supplement, as revised, submitted pursuant to 10 CFR 54.21(d),shall be included in the next scheduled update to the UFSAR required by 10 CFR 50.71(e)(4) following the issuance of this renewed operating license.
Until that update is complete, TVA may make changes to the programs and activities described in the supplement without prior Commission approval, provided that TVA evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.E.The UFSAR supplement, as revised, describes certain future activities to becompleted prior to the period of extended operation. TVA shall complete these activities no later than July 2, 2016, and shall notify the NRC in writing whenimplementation of these activities is complete and can be verified by NRC inspection. F.All capsules in the reactor vessel that are removed and tested must meet the testprocedures and reporting requirements of the most recent NRC-approved versionof the Boiling Water Reactor Vessels and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) appropriate for the configuration of the specimens in the capsule. Any changes to the BWRVIP ISP capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by10 CFR Part 50, Appendix H.G.This renewed license is effective as of the date of issuance and shall expiremidnight on July 2, 2036.FOR THE NUCLEAR REGULATORY COMMISSION/RA/J. E. Dyer, DirectorOffice of Nuclear Reactor RegulationAttachments:1.Unit 3 - Technical Specifications - Appendices A and BDate of Issuance: May 4, 2006