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MONTHYEARML0407200022004-03-24024 March 2004 RAI, NDE Examination of RPV Nozzle-to-Vessel Welds and Nozzle Blend Radii Project stage: RAI ML0433803212004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, in Service Inspection Program Project stage: Other ML0432206272004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Requests for Relief 2-ISI-22, and 3-ISI-18 for Examination of Reactor Pressure Vessel Nozzle-To-Vessel Shell Welds and Nozze Blend. Project stage: Other ML0433404292004-12-20020 December 2004 Withdrawal of Relief Requests 2-ISI-22 and 3-ISI-18 Re Nondestructive Examination of Reactor Pressure Vessel Nozzle-to-Vessel Welds and Nozzle Blend Radii Project stage: Withdrawal ML0523101262005-08-18018 August 2005 American Society of Mechanical Engineers RPV Welds Withdrawal of Requests Project stage: Withdrawal 2004-12-20
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Category:Letter
MONTHYEARIR 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 IR 05000269/20240032024-10-31031 October 2024 Integrated Inspection Report 05000269/2024003 and 05000270/2024003 and 05000287/2024003 (2) 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 ML24255A3322024-10-16016 October 2024 SLRA - Revised SE Letter ML24297A6172024-10-11011 October 2024 PCA Letter to NRC Oconee Hurricane Helene ML24269A0912024-10-0909 October 2024 Request for Withholding Information from Public Disclosure 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 ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) 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 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 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 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 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) ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification 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 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 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 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) 2024-09-03
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December 20, 2004 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 WITHDRAWAL OF RELIEF REQUEST REGARDING NONDESTRUCTIVE EXAMINATION OF REACTOR PRESSURE VESSEL NOZZLE-TO-VESSEL WELDS AND NOZZLE BLEND RADII (TAC NOS. MC0167 AND MC0168)
Dear Mr. Singer:
By letter dated July 25, 2003, as supplement by a letter dated November 15, 2004, the Tennessee Valley Authority (TVA) submitted Relief Requests Nos. 2-ISI-22 and 3-ISI-18 for Browns Ferry Units 2 and 3 from the inservice inspection requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, (ASME Code) for the volumetric (UT) examination of reactor pressure vessel (RPV) nozzle-to-vessel welds and inner radius sections. Instead, TVA proposed to use the technical basis of Report 108, BWR
[Boiling-Water Reactor] Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii, to (1) reduce the inspection of these areas from 100 percent to 25 percent each 10-year interval and (2) replace UT by enhanced remote visual VT-1 for RPV nozzles inner radius section and by enhanced direct visual VT-1 for RPV head nozzles. Subsequently, by letter dated November 15, 2004, you superseded the relief request in its entirety. The purpose of this letter is to advise that the above cited application is being treated as withdrawn.
Although your original request has been withdrawn, the Nuclear Regulatory Commission (NRC) staff found that a response to the request for additional information issued on March 24, 2004, was needed before the review could be completed. The NRC staff notes that timely responses to questions are necessary to ensure an efficient use of NRC resources and the completion of
K. Singer the review by your requested date. In the future, if a timely response cannot be provided, the NRC staff may decide to reject your application to allow resources to be redirected to other reviews.
This completes the staff's review of the July 25, 2003, submittal under TAC Nos. MC0167 and MC0168.
Sincerely,
/RA/
Eva A. Brown, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-260 and 50-269 cc: See next page
ML043340429 NRR-106 OFFICE PDII-2/PM PDII-2/LA PDII-2/SC NAME EBrown BClayton MMarshall DATE 12/17/04 12/17/04 12/20/04 Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Fredrick C. Mashburn Nuclear Operations Senior Program Manager Tennessee Valley Authority Nuclear Licensing 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael J. Lorek, General Manager Nuclear Engineering Mr. Timothy E. Abney, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place Browns Ferry Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Decatur, AL 35609 Mr. Michael D. Skaggs Site Vice President Senior Resident Inspector Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority Browns Ferry Nuclear Plant P.O. Box 2000 10833 Shaw Road Decatur, AL 35609 Athens, AL 35611-6970 General Counsel State Health Officer Tennessee Valley Authority Alabama Dept. of Public Health ET 11A RSA Tower - Administration 400 West Summit Hill Drive Suite 1552 Knoxville, TN 37902 P.O. Box 303017 Montgomery, AL 36130-3017 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing Chairman Tennessee Valley Authority Limestone County Commission 6A Lookout Place 310 West Washington Street 1101 Market Street Athens, AL 35611 Chattanooga, TN 37402-2801 Mr. Kurt L. Krueger, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609