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| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Swafford P D | | | addressee name = Swafford P |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000259 | | | docket = 05000259 |
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MONTHYEARML0820504122008-07-18018 July 2008 Technical Specifications (TS) Change TS-446 - Safety Limit Minimum Critical Power Ratio - Cycle 8 Operation Project stage: Request ML0830904042008-11-0606 November 2008 RAI Regarding a Revision to the Minimum Critical Power Ratio Project stage: RAI ML0834500652008-12-0505 December 2008 Unit 1 - Technical Specifications (TS) Change TS-446 - Safety Limit Minimum Critical Power Ratio (SLMCPR) - Cycle 8 Operation - Response to Request for Additional Information (RAI) Project stage: Response to RAI ML0930004962009-10-23023 October 2009 Browns, Ferry, Unit 1 - Technical Specifications Change TS-446 - Safety Limit Minimum Critical Power Ratio (SLMCPR) - Cycle 8 Operation (NRC TAC No. MD9255) Withdrawal of Request Project stage: Withdrawal ML0930303802009-11-0303 November 2009 Federal Register Notice - Withdrawal of Amendment Request Revising Technical Specification Section 2.1.1.2 Related to Cycle 8 Safety Limit Minimum Critical Power Ratio Project stage: Withdrawal ML0930303552009-11-0303 November 2009 Withdrawal of Amendment Request Revising Technical Specification Section 2.1.1.2 Related to Cycle 8 Safety Limit Minimum Critical Power Ratio (TAC MD9255) (TS-446) Project stage: Withdrawal 2008-07-18
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Category:Letter
MONTHYEARIR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24151A6322024-05-30030 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 3, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB..BROWNS FERRY NUCLEAR PLANT, UNIT 1 -WITHDRAWAL OF AMENDMENT REQUEST REVISING TECHNICAL SPECIFICATION SECTION 2.1.1.2 RELATED TO CYCLE 8 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NO. MD9255) (TS-446)
Dear Mr. Swafford:
The purpose of this letter is to acknowledge the October 23,2009, letter from Tennessee Valley Authority that withdrew a request for Nuclear Regulatory Commission (NRC) approval of an application for an amendment to Renewed Facility Operating License No. DPR-33 for the Browns Ferry Nuclear Plant, Unit 1. Your application dated July 18, 2008, as supplemented by letter dated December 5,2008, requested changes to the Cycle 8 safety limit minimum critical power ratio (SLMCPR) value for Unit 1. Specifically, the change would have lowered the numeric values of SLMCPR in Technical Specification Section 2.1.1.2 for one and two reactor recirculation loop operation to incorporate the results of the Unit 1 Cycle 8 SLMCPR analysis.
The NRC staff has terminated its review of the proposed change and TAC No. MD9255 has been closed. The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication.
If you have any questions, please contact me at (301) 415-2315.
Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
Notice of cc Distribution via 7590-01-P UNITED STATES NUCLEAR REGULATORY TENNESSEE VALLEY DOCKET NO. NOTICE OF WITHDRAWAL OF APPLICATION AMENDMENT TO FACILITY OPERATING The U.S. Nuclear Regulatory Commission (the Commission) has granted the request of Tennessee Valley Authority (the licensee) to withdraw its application dated July 18, 2008, as supplemented by letter dated December 5,2008, for proposed amendment to Renewed Facility Operating License No. DPR-33 for the Browns Ferry Nuclear Plant, Unit 1, located in Limestone County, Alabama. The proposed amendment would have revised the Technical Specifications (TS) to lower the numeric values of safety limit minimum critical power ratio (SLMCPR) in TS Section 2.1.1.2 for single and two reactor recirculation loop operation to incorporate the results of the Unit 1 Cycle 8 SLMCPR analysis.
The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the FEDERAL REGISTER on November 18, 2008 (73 FR 68456). However, by letter dated October 23,2009, the licensee withdrew the proposed change. For further details with respect to this action, see the application for amendment dated July 18, 2008, as supplemented by letter dated December 5, 2008, and the licensee's letter dated October 23, 2009, which withdrew the application for license amendment.
Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
-2 Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301-415-4737 or by email to pdr.resource@nrc.gov.
Dated at Rockville, Maryland, this 3 rd
- day of November 2009. FOR THE NUCLEAR REGULATORY COMMISSION IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation November 3, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT, UNIT 1 -WITHDRAWAL OF AMENDMENT REQUEST REVISING TECHNICAL SPECIFICATION SECTION 2.1.1.2 RELATED TO CYCLE 8 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (TAC NO. MD9255) (TS-446)
Dear Mr. Swafford:
The purpose of this letter is to acknowledge the October 23,2009, letter from Tennessee Valley Authority that withdrew a request for Nuclear Regulatory Commission (NRC) approval of an application for an amendment to Renewed Facility Operating License No. DPR-33 for the Browns Ferry Nuclear Plant, Unit 1. Your application dated July 18, 2008, as supplemented by letter dated December 5, 2008, requested changes to the Cycle 8 safety limit minimum critical power ratio (SLMCPR) value for Unit 1. Specifically, the change would have lowered the numeric values of SLMCPR in Technical Spedfication Section 2.1.1.2 for one and two reactor recirculation loop operation to incorporate the results of the Unit 1 Cycle 8 SLMCPR analysis.
The NRC staff has terminated its review of the proposed change and TAC No. MD9255 has been closed. The Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication.
If you have any questions, please contact me at (301) 415-2315.
Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
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PUBLIC LPL2-2 R1F RidsNrrDorlLpl2-2 RidsNrrPMBrownsFerry SLingam, NRR RidsNrrLABClayton RidsNrrDirsltsb RidsOgcRp MRazzaque, NRR RidsAcrsAcnw_MailCTR RidsNrrDorlDpr RidsRgn2MailCenter RidsNrrDssSrxb ADAMS Accession No Letter* ML093030355 FR Notice" ML093030380 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC LPL2-2/PM NAME EBrown BClayton TBoyce EBrown DATE 11/03/09 11/03/09 11/03/09 11/03/09 OFFICIAL RECORD COPY