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| | issue date = 12/06/2007 | | | issue date = 12/06/2007 |
| | title = 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 | | | title = 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 |
| | author name = Reyes L A | | | author name = Reyes L |
| | author affiliation = NRC/EDO | | | author affiliation = NRC/EDO |
| | addressee name = Cramer B | | | addressee name = Cramer B |
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| =Text= | | =Text= |
| {{#Wiki_filter:December 6, 2007 | | {{#Wiki_filter:December 6, 2007 The Honorable Bud Cramer Member, United States House of Representatives 200 Pratt Avenue, NE, Suite A Huntsville, Alabama 35801 |
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| The Honorable Bud Cramer Member, United States House of Representatives 200 Pratt Avenue, NE, Suite A Huntsville, Alabama 35801 | |
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| ==Dear Congressman Cramer:== | | ==Dear Congressman Cramer:== |
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| 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. | | 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. | | 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. |
| 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. | | 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. |
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| 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. | | 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, | | Sincerely, |
| /RA/ Luis A. Reyes Executive Director for Operations
| | /RA/ |
| | Luis A. Reyes Executive Director for Operations |
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| ML073240396 EDO-002}} | | 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}} |
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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
MONTHYEARML24289A1232024-10-24024 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 CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24190A1292024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints ML24185A1512024-07-0303 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) ML24176A1022024-06-24024 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 IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A2462024-05-20020 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 ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision ML24115A1652024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
[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
[Table view] |
Text
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