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| {{#Wiki_filter:TENNESSEE VALLEY AUTHORITYDOCKET NO. 50-260BROWNS FERRY NUCLEAR PLANT, UNIT 2RENEWED FACILITY OPERATING LICENSERenewed License No. DPR-521.The Nuclear Regulatory Commission (NRC or the Commission), having previously madethe findings set forth in License DPR-52 issued on June 28, 1974, 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 2 (the facility) has beensubstantially completed in conformity with Construction Permit No. CPPR-30 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-52H. 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-52,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 nuclear materialas authorized by this renewed license will be in accordance with the Commission'sregulations 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-52 which is hereby issued to read asfollows:A. This renewed license applies to the Browns Ferry Nuclear Plant, Unit 2, a boilingwater nuclear reactor and associated equipment (the facility), owned by TVA. Thefacility is located in Limestone County, Alabama, and is described in the "FinalSafety Analysis Report" (Amendment 9) as supplemented and amended (Amendments 10 through 55), the licensee's Draft Environmental Statement andsupplement thereto dated July 1971, and November 8, 1971, respectively, and thelicensee's Final Environmental Statement dated September 1, 1972.B. Subject to the conditions and requirements incorporated herein, the Commissionhereby licenses TVA:(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 40 and 70, to receive, possess, anduse 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;(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 Renewed License No. DPR-52sealed neutron sources for reactor startup, sealed sources for reactorinstrumentation 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: | | {{#Wiki_filter:TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 RENEWED FACILITY OPERATING LICENSE Renewed License No. DPR-52 |
| 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, as revisedthrough Amendment No. 295, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordancewith the Technical Specifications.For Surveillance Requirements (SRs) that are new in Amendment 253 toFacility Operating License DPR-52, the first performance is due at the endof the first surveillance interval that begins at implementation of Amendment 253. For SRs that existed prior to Amendment 253, includingSRs 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 the surveillance waslast performed prior to implementation of Amendment 253.(3) The licensee is authorized to relocate certain requirements included inAppendix A and the former Appendix B to licensee-controlled documents. | | : 1. The Nuclear Regulatory Commission (NRC or the Commission), having previously made the findings set forth in License DPR-52 issued on June 28, 1974, has now found that: |
| Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's Renewed License No. DPR-52application dated September 6, 1996; as supplemented May 1, August14, 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, andJune 2, 5, 10 and 19, 1998; evaluated in the NRC staff's SafetyEvaluation enclosed with this amendment. This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment.(4) Deleted. | | A. The application for license filed by the Tennessee Valley Authority (TVA or the licensee) 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 2 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-30 and the application, as amended, the provisions of the Act and the rules and regulations 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 operating license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for the facility, and that any changes made to the facilitys current licensing basis in order to comply with 10 CFR 54.29(a) are in accordance with the Act and the Commissions regulations; D. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; E. There is reasonable assurance: (i) that the activities authorized by the renewed operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; F. The licensee is technically and financially qualified to engage in the activities authorized 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; |
| (5) Classroom and simulator training on all power uprate related changesthat affect operator performance will be conducted prior to operating atuprated conditions. 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.(5)(a) Deleted. | | |
| (6) Deleted. | | H. The issuance of this renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; I. The staff, after weighing the environmental, economic, technical and other benefits of the facility against environmental costs, and considering available alternatives, has found that the adverse environmental impacts of license renewal are not so great that preserving the option of license renewal would be unreasonable, the issuance of Renewed Facility Operating License No. DPR-52, 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; and J. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this renewed license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70, including 10 CFR Sections 30.33, 40.32, 70.23, and 70.31. |
| (7) Deleted. | | : 2. The Atomic Safety and Licensing Board having dismissed the proceeding relating to the licensing action in a "Memorandum and Order," dated November 27, 1973, is superseded by Renewed Facility Operating License No. DPR-52 which is hereby issued to read as follows: |
| (8) Deleted. | | A. This renewed license applies to the Browns Ferry Nuclear Plant, Unit 2, a boiling water nuclear reactor and associated equipment (the facility), owned by 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 55), the licensee's Draft Environmental Statement and supplement thereto dated July 1971, and November 8, 1971, respectively, and the licensee's Final Environmental Statement dated September 1, 1972. |
| (9) Deleted. | | B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses TVA: |
| (10) Deleted. | | (1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated location in Limestone County, Alabama, in accordance with the procedures and limitations set forth in this renewed license; (2) Pursuant to the Act and 10 CFR Parts 40 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; (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 Renewed License No. DPR-52 |
| (11) 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 dated September 10, 2004, and supplemented on October 22, 2004.(12) Deleted. | | |
| (13) Deleted. Renewed License No. DPR-52(14) 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.(15) 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. | | 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 not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. |
| 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 June 28, 2014, 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 thetest procedures and reporting requirements of the most recent NRC-approvedversion of the Boiling Water Reactor Vessels and Internals Project (BWRVIP) | | C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: |
| 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 toimplementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC,as required by 10 CFR Part 50, Appendix H. Renewed License No. DPR-52G.This renewed license is effective as of the date of issuance and shall expiremidnight on June 28, 2034.FOR THE NUCLEAR REGULATORY COMMISSION/RA/J. E. Dyer, DirectorOffice of Nuclear Reactor RegulationAttachments:1.Unit 2 - Technical Specifications - Appendices A and BDate of Issuance: May 4, 2006}} | | 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 Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal. |
| | (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 295, 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 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 253. For SRs that existed prior to Amendment 253, 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 the surveillance was last performed prior to implementation of Amendment 253. |
| | (3) The licensee is authorized to relocate certain requirements included in Appendix 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 Renewed License No. DPR-52 |
| | |
| | application dated September 6, 1996; as supplemented May 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's Safety 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 that affect operator performance will be conducted prior to operating at uprated conditions. Simulator changes that are consistent with power uprate conditions will be made and simulator fidelity will be validated in accordance with ANSI/ANS 3.5-1985. Training and the plant simulator will be modified, as necessary, to incorporate changes identified during startup testing. This amendment is effective immediately. |
| | (5)(a) Deleted. |
| | (6) Deleted. |
| | (7) Deleted. |
| | (8) Deleted. |
| | (9) Deleted. |
| | (10) Deleted. |
| | (11) The licensee shall fully implement and maintain in effect all provisions of the 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 dated September 10, 2004, and supplemented on October 22, 2004. |
| | (12) Deleted. |
| | (13) Deleted. |
| | Renewed License No. DPR-52 |
| | |
| | (14) Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions 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 protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. |
| | (15) The licensee shall maintain the Augmented Quality Program for the Standby Liquid Control System to provide quality control elements to ensure component reliability for the required alternative source term function 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 be completed prior to the period of extended operation. TVA shall complete these activities no later than June 28, 2014, and shall notify the NRC in writing when implementation 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 test procedures and reporting requirements of the most recent NRC-approved version of 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 by 10 CFR Part 50, Appendix H. |
| | Renewed License No. DPR-52 |
| | |
| | G. This renewed license is effective as of the date of issuance and shall expire midnight on June 28, 2034. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments: |
| | : 1. Unit 2 - Technical Specifications - Appendices A and B Date of Issuance: May 4, 2006 Renewed License No. DPR-52}} |
Letter Sequence Other |
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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-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-083, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use CNL-22-056, Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-04-28028 April 2022 Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-009, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2022-03-31031 March 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative CNL-21-002, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance.2021-12-0303 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance. CNL-21-090, Application to Adopt TSTF-568-A, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2, Revision 2 (BFN TS-539)2021-11-19019 November 2021 Application to Adopt TSTF-568-A, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2, Revision 2 (BFN TS-539) CNL-21-020, Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2021-11-0505 November 2021 Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535)2021-07-23023 July 2021 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535) CNL-21-050, License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2021-05-29029 May 2021 License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN82021-04-29029 April 2021 Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- CNL-21-008, Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532)2021-03-0505 March 2021 Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532) CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)2020-08-14014 August 2020 License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re CNL-20-002, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529)2020-07-17017 July 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529) CNL-20-044, License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis2020-05-0606 May 2020 License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-125, Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition2019-12-19019 December 2019 Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition CNL-19-009, License Amendment Request to Revise Emergency Plan Staff Augmentation Times (TS-515)2019-09-18018 September 2019 License Amendment Request to Revise Emergency Plan Staff Augmentation Times (TS-515) CNL-19-070, TVA Request for Extension of Implementation Due Dates of Modifications 102 and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor2019-07-0303 July 2019 TVA Request for Extension of Implementation Due Dates of Modifications 102 and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor CNL-19-034, to TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3..2019-03-0808 March 2019 to TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3.. CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-11-29029 November 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-099, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results2018-07-23023 July 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results ML18171A3372018-07-10010 July 2018 Issuance of Amendment to Revise License Condition 2.C(18)(a)3 CNL-18-085, License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme2018-06-15015 June 2018 License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-056, Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2017-08-15015 August 2017 Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-014, Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Pro2017-04-0505 April 2017 Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Proce CNL-16-155, Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and To..2017-01-17017 January 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and To.. CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-010, Application to Modify Technical Specification 4.3.1.2, Fuel Storage Criticality (TS-508)2016-08-12012 August 2016 Application to Modify Technical Specification 4.3.1.2, Fuel Storage Criticality (TS-508) CNL-16-016, License Amendment Request (BFN TS-509) to Change the Completion Date of Cyber Security Plan Implementation Milestone 82016-07-14014 July 2016 License Amendment Request (BFN TS-509) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 CNL-16-068, Update to License Amendment Request, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2016-03-28028 March 2016 Update to License Amendment Request, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.2015-09-16016 September 2015 Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And. CNL-15-074, Update to License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants2015-06-19019 June 2015 Update to License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants CNL-15-029, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502) 2023-03-30
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 RENEWED FACILITY OPERATING LICENSE Renewed License No. DPR-52
- 1. The Nuclear Regulatory Commission (NRC or the Commission), having previously made the findings set forth in License DPR-52 issued on June 28, 1974, has now found that:
A. The application for license filed by the Tennessee Valley Authority (TVA or the licensee) 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 2 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-30 and the application, as amended, the provisions of the Act and the rules and regulations 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 operating license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for the facility, and that any changes made to the facilitys current licensing basis in order to comply with 10 CFR 54.29(a) are in accordance with the Act and the Commissions regulations; D. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; E. There is reasonable assurance: (i) that the activities authorized by the renewed operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; F. The licensee is technically and financially qualified to engage in the activities authorized 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;
H. The issuance of this renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; I. The staff, after weighing the environmental, economic, technical and other benefits of the facility against environmental costs, and considering available alternatives, has found that the adverse environmental impacts of license renewal are not so great that preserving the option of license renewal would be unreasonable, the issuance of Renewed Facility Operating License No. DPR-52, 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; and J. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this renewed license will be in accordance with the Commission'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 the licensing action in a "Memorandum and Order," dated November 27, 1973, is superseded by Renewed Facility Operating License No. DPR-52 which is hereby issued to read as follows:
A. This renewed license applies to the Browns Ferry Nuclear Plant, Unit 2, a boiling water nuclear reactor and associated equipment (the facility), owned by 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 55), the licensee's Draft Environmental Statement and supplement thereto dated July 1971, and November 8, 1971, respectively, and the licensee's Final Environmental Statement dated September 1, 1972.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses TVA:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated location in Limestone County, Alabama, in accordance with the procedures and limitations set forth in this renewed license; (2) Pursuant to the Act and 10 CFR Parts 40 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; (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 Renewed License No. DPR-52
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 not separate, 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 the conditions 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 Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 295, 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 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 253. For SRs that existed prior to Amendment 253, 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 the surveillance was last performed prior to implementation of Amendment 253.
(3) The licensee is authorized to relocate certain requirements included in Appendix 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 Renewed License No. DPR-52
application dated September 6, 1996; as supplemented May 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's Safety 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 that affect operator performance will be conducted prior to operating at uprated conditions. Simulator changes that are consistent with power uprate conditions will be made and simulator fidelity will be validated in accordance with ANSI/ANS 3.5-1985. Training and the plant simulator will be modified, as necessary, to incorporate changes identified during startup testing. This amendment is effective immediately.
(5)(a) Deleted.
(6) Deleted.
(7) Deleted.
(8) Deleted.
(9) Deleted.
(10) Deleted.
(11) The licensee shall fully implement and maintain in effect all provisions of the 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 dated September 10, 2004, and supplemented on October 22, 2004.
(12) Deleted.
(13) Deleted.
Renewed License No. DPR-52
(14) Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions 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 protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(15) The licensee shall maintain the Augmented Quality Program for the Standby Liquid Control System to provide quality control elements to ensure component reliability for the required alternative source term function 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 be completed prior to the period of extended operation. TVA shall complete these activities no later than June 28, 2014, and shall notify the NRC in writing when implementation 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 test procedures and reporting requirements of the most recent NRC-approved version of 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 by 10 CFR Part 50, Appendix H.
Renewed License No. DPR-52
G. This renewed license is effective as of the date of issuance and shall expire midnight on June 28, 2034.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Unit 2 - Technical Specifications - Appendices A and B Date of Issuance: May 4, 2006 Renewed License No. DPR-52