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| | number = ML080590376 | | | number = ML080590376 |
| | issue date = 03/13/2008 | | | issue date = 03/13/2008 |
| | title = Browns Ferry, Unit 3, Request for Additional Information, Third 10-Year Interval Inservice Inspection Program Plan Relief Request RR-3-ISI-23 | | | title = Request for Additional Information, Third 10-Year Interval Inservice Inspection Program Plan Relief Request RR-3-ISI-23 |
| | author name = Brown E A | | | author name = Brown E |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 |
| | addressee name = Campbell W R | | | addressee name = Campbell W |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000296 | | | docket = 05000296 |
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| =Text= | | =Text= |
| {{#Wiki_filter:March 13, 2008 | | {{#Wiki_filter:March 13, 2008 Mr. William R. Campbell, Jr. |
| | | Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
| Mr. William R. Campbell, Jr. | |
| Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BROWNS FERRY NUCLEAR PLANT, UNIT 3 C REQUEST FOR ADDITIONAL INFORMATION FOR THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST RR-3-ISI-23 (TAC NO. MD6749) | | BROWNS FERRY NUCLEAR PLANT, UNIT 3 C REQUEST FOR ADDITIONAL INFORMATION FOR THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST RR-3-ISI-23 (TAC NO. MD6749) |
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| ==Dear Mr. Campbell:== | | ==Dear Mr. Campbell:== |
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| By letter dated August 24, 2007, the Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item Nos. B3.90 and B3.100 and ASME Code Case N-648-1 Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessels, Section XI, Division 1 requirements based on it being impractical to perform the required examinations. The U.S. Nuclear Regulatory Commission (NRC) staff requires additional information in order to complete its evaluation of Request for Relief 3-ISI-23. | | By letter dated August 24, 2007, the Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item Nos. B3.90 and B3.100 and ASME Code Case N-648-1 Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessels, Section XI, Division 1 requirements based on it being impractical to perform the required examinations. The U.S. Nuclear Regulatory Commission (NRC) staff requires additional information in order to complete its evaluation of Request for Relief 3-ISI-23. |
| | | A response to the enclosed Request for Additional Information is needed before the NRC staff can complete the review. This request was discussed with Mr. James Emens of your staff on March 11, 2007, and it was agreed that TVA would respond by March 28, 2008. |
| A response to the enclosed Request for Additional Information is needed before the NRC staff can complete the review. This request was discussed with Mr. James Emens of your staff on March 11, 2007, and it was agreed that TVA would respond by March 28, 2008. | | If you have any questions, please contact me at (301) 415-2315. |
| | | Sincerely, |
| If you have any questions, please contact me at (301) 415-2315. | | /RA/ |
| | | Eva A. Brown, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-296 |
| Sincerely, /RA/ Eva A. Brown, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| Docket No. 50-296 | |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information | | Request for Additional Information cc w/enclosure: See next page |
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| cc w/enclosure: See next page | |
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| ML080590376 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA DCI/CVIB /BC LPL2-2/BC NAME EBrown BClayton MMitchell By memo dated TBocye DATE 03 / 13 /08 03 / 12 /08 01 / 31/08 03 / 13 /08
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| REQUEST FOR ADDITIONAL INFORMATION RELIEF REQEST 3-ISI-23 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-296
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| American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 requires a volumetric examination of essentially 100 percent of the reactor pressure vessel (RPV) nozzle welds as depicted in ASME Code, Section XI, Figure IWB-2500-7(a). ASME Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.100 requires a volumetric examination of essentially 100 percent of the RPV nozzle inner radius as depicted in ASME Code, Section XI, Figure IWB-2500-7(a). The licensee invoked ASME Code Case N-648-1, which allows one to perform an enhanced VT-1 visual examination of the inner radius of the RPV nozzles in lieu of a volumetric examination as required by the ASME Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.100.
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| : 1. The volumetric examinations for all the RPV nozzle-to-vessel welds and the enhanced VT-1 visual examinations of the inner radii of all the RPV nozzles provided in Table 1 of the original submittal and Weld Examination Report R-057 appear to be inconsistent.
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| Further, the information in Table 1 and Weld Examination Report R-057 appear to be inconsistent with the list of RPV nozzle-to-vessel welds and RPV nozzle inner radii listed on page E2-4 of the relief request (RR) as components addressed under RR 3-ISI-23.
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| Provide two separate tables listing the results of the volumetric examinations for all the RPV nozzle-to-vessel welds and the enhanced VT-1 visual examinations of the inner radii of all the RPV nozzles.
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| : 2. In reviewing the examination results, it appears that the volumetric examination coverages were in the range of 22 to 42 percent and a number of enhanced VT-1 visual examination results were in the 40 percent range. If this is correct, provide further basis why these limited examinations provide reasonable assurance of structural integrity of the subject welds and components. As part of this basis, address whether there are any mechanisms that may be expected to cause service-induced degradation of the subject components.
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| Enclosure Page 1 of 2 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT
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| Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. James R. Douet Vice President Nuclear Support Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. H. Rick Rogers Vice President Nuclear Engineering & Technical Services Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. D. Tony Langley, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609
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| General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902
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| Mr. John C. Fornicola, General Manager Nuclear Assurance Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Steven M. Douglas General Manager Browns Ferry Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609
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| Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. James E. Emens, Jr., Interim Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609
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| James B. Baptist Browns Ferry Senior Project Engineer Division of Reactor Projects, Branch 6 U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW.
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| Suite 24T85 Atlanta, GA 30303-8931
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| Tomy A. Nazario Browns Ferry Project Engineer Division of Reactor Projects, Branch 6 U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW.
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| Suite 24T85 Atlanta, GA 30303-8931
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| Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017
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| Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611
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| Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. Michael A. Purcell Senior Licensing Manager Nuclear Power Group Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
| | ML080590376 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA DCI/CVIB /BC LPL2-2/BC NAME EBrown BClayton MMitchell TBocye By memo dated DATE 03 / 13 /08 03 / 12 /08 01 / 31/08 03 / 13 /08 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQEST 3-ISI-23 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-296 American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 requires a volumetric examination of essentially 100 percent of the reactor pressure vessel (RPV) nozzle welds as depicted in ASME Code, Section XI, Figure IWB-2500-7(a). ASME Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.100 requires a volumetric examination of essentially 100 percent of the RPV nozzle inner radius as depicted in ASME Code, Section XI, Figure IWB-2500-7(a). The licensee invoked ASME Code Case N-648-1, which allows one to perform an enhanced VT-1 visual examination of the inner radius of the RPV nozzles in lieu of a volumetric examination as required by the ASME Code, Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.100. |
| | : 1. The volumetric examinations for all the RPV nozzle-to-vessel welds and the enhanced VT-1 visual examinations of the inner radii of all the RPV nozzles provided in Table 1 of the original submittal and Weld Examination Report R-057 appear to be inconsistent. |
| | Further, the information in Table 1 and Weld Examination Report R-057 appear to be inconsistent with the list of RPV nozzle-to-vessel welds and RPV nozzle inner radii listed on page E2-4 of the relief request (RR) as components addressed under RR 3-ISI-23. |
| | Provide two separate tables listing the results of the volumetric examinations for all the RPV nozzle-to-vessel welds and the enhanced VT-1 visual examinations of the inner radii of all the RPV nozzles. |
| | : 2. In reviewing the examination results, it appears that the volumetric examination coverages were in the range of 22 to 42 percent and a number of enhanced VT-1 visual examination results were in the 40 percent range. If this is correct, provide further basis why these limited examinations provide reasonable assurance of structural integrity of the subject welds and components. As part of this basis, address whether there are any mechanisms that may be expected to cause service-induced degradation of the subject components. |
| | Enclosure |
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| Mr. Michael D. Skaggs Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 | | Page 1 of 2 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT cc: |
| | Mr. Ashok S. Bhatnagar Senior Vice President Mr. Steven M. Douglas Nuclear Generation Development General Manager and Construction Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. James R. Douet Ms. Beth A. Wetzel, Manager Vice President Corporate Nuclear Licensing Nuclear Support and Industry Affairs Tennessee Valley Authority Tennessee Valley Authority 3R Lookout Place 4X Blue Ridge 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. H. Rick Rogers Mr. James E. Emens, Jr., Interim Manager Vice President Licensing and Industry Affairs Nuclear Engineering & Technical Services Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 3R Lookout Place P.O. Box 2000 1101 Market Street Decatur, AL 35609 Chattanooga, TN 37402-2801 James B. Baptist Mr. D. Tony Langley, Manager Browns Ferry Senior Project Engineer Licensing and Industry Affairs Division of Reactor Projects, Branch 6 Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 61 Forsyth Street, SW. |
| | P.O. Box 2000 Suite 24T85 Decatur, AL 35609 Atlanta, GA 30303-8931 General Counsel Tomy A. Nazario Tennessee Valley Authority Browns Ferry Project Engineer 6A West Tower Division of Reactor Projects, Branch 6 400 West Summit Hill Drive U.S. Nuclear Regulatory Commission Knoxville, TN 37902 61 Forsyth Street, SW. |
| | Suite 24T85 Mr. John C. Fornicola, General Manager Atlanta, GA 30303-8931 Nuclear Assurance Tennessee Valley Authority Senior Resident Inspector 3R Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street Browns Ferry Nuclear Plant Chattanooga, TN 37402-2801 10833 Shaw Road Athens, AL 35611-6970 |
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| Mr. William R. Campbell, Jr. | | State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael A. Purcell Senior Licensing Manager Nuclear Power Group Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. William R. Campbell, Jr. |
| Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801}} | | Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801}} |
Letter Sequence RAI |
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MONTHYEARML0805903762008-03-13013 March 2008 Request for Additional Information, Third 10-Year Interval Inservice Inspection Program Plan Relief Request RR-3-ISI-23 Project stage: RAI ML0824805732008-09-24024 September 2008 Relief Request Associated with Third 10 Year Interval Inservice Inspection Examination Requirements (TAC No. MD6749) (3-ISI-23) Project stage: Other 2008-03-13
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24255A5822024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 ML24255A5802024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 - Email from Jessica Hammock to James Barstow ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A0272024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to TVAs Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to TVAs Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to TVAs Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to TVAs Request to Revised the TVA Plants Radiological Emergency Plans ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding TVAs Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) ML21173A1042021-06-21021 June 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to TS 3.8.6 ML21041A5422021-02-10010 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt 10 CFR 50.69 ML21041A5432021-02-0505 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Draft Request for Additional Information Regarding 10 CFR 50.69 LAR ML21026A1652021-01-26026 January 2021 Document Request for Browns Ferry Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-02 ML20297A3012020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt TSTF-425 ML20296A3782020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Incorporate TMRE ML20294A3762020-09-23023 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Adopt TSTF-425 ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information ML20224A4732020-08-11011 August 2020 Requalification Program Inspection Browns Ferry Nuclear ML20195B1302020-07-13013 July 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Alternative Request No. 0-ISI-47 ML20149K3212020-05-27027 May 2020 RP Inspection Document Request, Browns Ferry 2020-003 ML20254A3032020-05-13013 May 2020 Request for Supporting Information for the Browns Ferry, Units 1, 2, and 3 Seismic Probabilistic Risk Assessment Audit Review ML20054B8592020-02-20020 February 2020 Emergency Preparedness Program Inspection Request for Information ML20014E6552020-01-14014 January 2020 01 RP Inspection Document Request ML19196A0752019-07-12012 July 2019 NRR E-mail Capture - Final RAIs Browns Ferry Nuclear, Units 1, 2, 3 - Application to Revise Technical Specifications to Adopt TSTF-542 Revision 2, Reactor Pressure Vessel Water Inventory Control ML19116A0712019-06-0303 June 2019 Request for Additional Information Related Resubmittal of Proposed Alternative Request No. 1-ISI-27 for the Period of Extended Operation ML18331A5442018-12-0606 December 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - (Non-Proprietary) ML18317A1642018-11-20020 November 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - Non-Proprietary ML18263A1412018-09-11011 September 2018 NRR E-mail Capture - Browns Ferry Unit 1: RAI Associated with Relief Request 1-ISI-28 ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18108A1872018-04-18018 April 2018 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000259/2018411, 05000260/2018411, and 05000296/2018411 ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17216A0062017-08-18018 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to LAR to Revise Modifications and Implementations Related to NFPA 805 for Fire Protection for Light Water Reactor Generating Plants (CAC Nos. MF9814-MF9816) ML17163A0502017-06-0808 June 2017 NRR E-mail Capture - RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257 ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML16288A0182016-10-27027 October 2016 Browns Ferry Nuclear Plant, Units 2 and 3 - RAI Related to Relief Request for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI Requirements (CAC Nos. MF7795 and MF7796) ML16236A0732016-08-31031 August 2016 Request for Additional Information Related to License Amendment Request to Add New Technical Specification 3.3.8.3 ML16203A0272016-07-25025 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (CAC Nos. MF6738, MF6739, and MF6740) ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16187A2932016-07-21021 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743) ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate 2024-09-10
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March 13, 2008 Mr. William R. Campbell, Jr.
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, UNIT 3 C REQUEST FOR ADDITIONAL INFORMATION FOR THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST RR-3-ISI-23 (TAC NO. MD6749)
Dear Mr. Campbell:
By letter dated August 24, 2007, the Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item Nos. B3.90 and B3.100 and ASME Code Case N-648-1 Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessels,Section XI, Division 1 requirements based on it being impractical to perform the required examinations. The U.S. Nuclear Regulatory Commission (NRC) staff requires additional information in order to complete its evaluation of Request for Relief 3-ISI-23.
A response to the enclosed Request for Additional Information is needed before the NRC staff can complete the review. This request was discussed with Mr. James Emens of your staff on March 11, 2007, and it was agreed that TVA would respond by March 28, 2008.
If you have any questions, please contact me at (301) 415-2315.
Sincerely,
/RA/
Eva A. Brown, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-296
Enclosure:
Request for Additional Information cc w/enclosure: See next page
ML080590376 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA DCI/CVIB /BC LPL2-2/BC NAME EBrown BClayton MMitchell TBocye By memo dated DATE 03 / 13 /08 03 / 12 /08 01 / 31/08 03 / 13 /08 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQEST 3-ISI-23 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-296 American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 requires a volumetric examination of essentially 100 percent of the reactor pressure vessel (RPV) nozzle welds as depicted in ASME Code,Section XI, Figure IWB-2500-7(a). ASME Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.100 requires a volumetric examination of essentially 100 percent of the RPV nozzle inner radius as depicted in ASME Code,Section XI, Figure IWB-2500-7(a). The licensee invoked ASME Code Case N-648-1, which allows one to perform an enhanced VT-1 visual examination of the inner radius of the RPV nozzles in lieu of a volumetric examination as required by the ASME Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.100.
- 1. The volumetric examinations for all the RPV nozzle-to-vessel welds and the enhanced VT-1 visual examinations of the inner radii of all the RPV nozzles provided in Table 1 of the original submittal and Weld Examination Report R-057 appear to be inconsistent.
Further, the information in Table 1 and Weld Examination Report R-057 appear to be inconsistent with the list of RPV nozzle-to-vessel welds and RPV nozzle inner radii listed on page E2-4 of the relief request (RR) as components addressed under RR 3-ISI-23.
Provide two separate tables listing the results of the volumetric examinations for all the RPV nozzle-to-vessel welds and the enhanced VT-1 visual examinations of the inner radii of all the RPV nozzles.
- 2. In reviewing the examination results, it appears that the volumetric examination coverages were in the range of 22 to 42 percent and a number of enhanced VT-1 visual examination results were in the 40 percent range. If this is correct, provide further basis why these limited examinations provide reasonable assurance of structural integrity of the subject welds and components. As part of this basis, address whether there are any mechanisms that may be expected to cause service-induced degradation of the subject components.
Enclosure
Page 1 of 2 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT cc:
Mr. Ashok S. Bhatnagar Senior Vice President Mr. Steven M. Douglas Nuclear Generation Development General Manager and Construction Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. James R. Douet Ms. Beth A. Wetzel, Manager Vice President Corporate Nuclear Licensing Nuclear Support and Industry Affairs Tennessee Valley Authority Tennessee Valley Authority 3R Lookout Place 4X Blue Ridge 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. H. Rick Rogers Mr. James E. Emens, Jr., Interim Manager Vice President Licensing and Industry Affairs Nuclear Engineering & Technical Services Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 3R Lookout Place P.O. Box 2000 1101 Market Street Decatur, AL 35609 Chattanooga, TN 37402-2801 James B. Baptist Mr. D. Tony Langley, Manager Browns Ferry Senior Project Engineer Licensing and Industry Affairs Division of Reactor Projects, Branch 6 Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 61 Forsyth Street, SW.
P.O. Box 2000 Suite 24T85 Decatur, AL 35609 Atlanta, GA 30303-8931 General Counsel Tomy A. Nazario Tennessee Valley Authority Browns Ferry Project Engineer 6A West Tower Division of Reactor Projects, Branch 6 400 West Summit Hill Drive U.S. Nuclear Regulatory Commission Knoxville, TN 37902 61 Forsyth Street, SW.
Suite 24T85 Mr. John C. Fornicola, General Manager Atlanta, GA 30303-8931 Nuclear Assurance Tennessee Valley Authority Senior Resident Inspector 3R Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street Browns Ferry Nuclear Plant Chattanooga, TN 37402-2801 10833 Shaw Road Athens, AL 35611-6970
State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael A. Purcell Senior Licensing Manager Nuclear Power Group Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. William R. Campbell, Jr.
Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801