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MONTHYEARML0732407332007-12-0606 December 2007 G20070793/LTR-07-0754/EDATS: SECY-2007-0507 - Rep. Bud Cramer Ltr. Potential Impact of Proposed Rock Quarry on Operations at the Browns Ferry Nuclear Plant Project stage: Other 2007-12-06
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application 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 ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation 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 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills 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 ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[Table view] Category:Congressional Correspondence
MONTHYEARCY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 19712011-07-14014 July 2011 G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 ML0732407332007-12-0606 December 2007 G20070793/LTR-07-0754/EDATS: SECY-2007-0507 - Rep. Bud Cramer Ltr. Potential Impact of Proposed Rock Quarry on Operations at the Browns Ferry Nuclear Plant ML0731304702007-11-0606 November 2007 G20070793/LTR-07-0754/EDATS: SECY-2007-0507 - Ltr. Rep. Bud Cramer Potential Impact of Proposed Rock Quarry on Operations at the Browns Ferry Nuclear Plant ML0715104232007-07-20020 July 2007 G20070352/LTR-07-0353/EDATS: SECY-2007-0147 - Ltr. Bennie G. Thompson & James R. Langevin Cybersecurity at Nuclear Power Plants ML0713703072007-05-15015 May 2007 G20070352/LTR-07-0353/EDATS: SECY-2007-0147 - Ltr. Bennie G. Thompson & James R. Langevin Cybersecurity at Nuclear Power Plants ML0318205932003-06-0606 June 2003 G20030355/LTR-03-0402 - Sen. Richard Shelby Ltr. Browns Ferry ML18283A5101976-05-21021 May 1976 Letter Urges Permission Be Granted for Loading & Testing of Browns Ferry ML18352A4271976-05-20020 May 1976 05/20/1976 Letter Energy Supply and Rising Costs for Electrical Service ML18283A5571976-05-0606 May 1976 Transmitting Letter from Tennessee Valley Public Power Association & Tennessee Valley Industrial Committee Letter Requesting Using Influence to Gain Compliance Regarding Browns Ferry Process 2011-07-14
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December 6, 2007 The Honorable Bud Cramer Member, United States House of Representatives 200 Pratt Avenue, NE, Suite A Huntsville, Alabama 35801
Dear Congressman Cramer:
On behalf of the U.S. Nuclear Regulatory Commission (NRC), I am responding to your letter of November 6, 2007, concerning the effects of a proposed relocation of a rock quarry to the Tanner Community near the Browns Ferry Nuclear Plant (BFN). My staff has been in contact with the Tennessee Valley Authority (TVA) who is the licensee for BFN. They have confirmed that they are aware of the concerns expressed in your letter, and are not aware of any regulatory actions required at this time. If however, TVA does identify a regulatory issue, it is expected that TVA would follow our process described below.
The licensee has the responsibility under Title 10 to the Code of Federal Regulations (10 CFR) to assess issues that affect safe operation of their facility, and the NRC has responsibility to review this information to ensure that the facility meets NRC requirements. The NRC does not have the authority to regulate other industrial facilities, but we will continue to regulate the safe and secure use of nuclear materials, including any facility changes, for the public good.
TVA must meet NRC-promulgated regulations that ensure safety in nuclear facility siting, design, and operation in 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, and Part 100, Reactor Site Criteria. In general terms, nuclear power plants are robust facilities that are designed to withstand a variety of events, including earthquakes.
Additionally, for changes to the facility, TVA is required by 10 CFR Section 50.59 to assess whether the changes affect the design basis for the facility as reviewed and approved by the NRC. If those changes have the potential to result in a significant increase in the likelihood or consequences of a plant event or significantly affect the ability of the licensee to respond to a plant event, an analysis is required to be submitted to the NRC for review.
I would like to assure you that the NRC has and will continue to carry out its authority in regulating NPP while ensuring the adequate protection of public health and safety, promote the common defense and security, and protect the environment. Should you need additional information, please feel free to contact Ms. Rebecca L. Schmidt, Director, Office of Congressional Affairs, at (301) 415-1776.
Sincerely,
/RA/
Luis A. Reyes Executive Director for Operations
ML073240396 EDO-002 OFFICE LPLII-2/PM LPLII-2LA Tech Editor LPLII-2/BC DORL/D NRR/D OCA EDO NAME EBrown BClayton HChang TBoyce TMcGinty for JDyer RSchmidt LReyes (via mail) CHaney DATE 11/26/07 11/26/07 11/23/07 11/21/07 11/21/07 12/03/07 12/04/07 12/06/07