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| | issue date = 07/01/2009 | | | issue date = 07/01/2009 |
| | title = Withdrawal of Relief Request (2-ISI-22) for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping | | | title = Withdrawal of Relief Request (2-ISI-22) for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping |
| | author name = Brown E A | | | author name = Brown E |
| | 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 = 05000260 | | | docket = 05000260 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 1,2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT UNIT 2 -WITHDRAWAL OF RELIEF REQUEST (2-ISI-22) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 1,2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
| FOR REPAIR OF CLASSES 1, 2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME1320) | | |
| | ==SUBJECT:== |
| | BROWNS FERRY NUCLEAR PLANT UNIT 2 - WITHDRAWAL OF RELIEF REQUEST (2-ISI-22) FOR REPAIR OF CLASSES 1, 2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME1320) |
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| ==Dear Mr. Swafford:== | | ==Dear Mr. Swafford:== |
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| By letter dated May 18, 2009, the Tennessee Valley Authority, the licensee submitted a relief request (RR) for Browns Ferry Nuclear Power Plant, Unit 2 to the U.S. Nuclear Regulatory Commission (NRC). The proposed RR was to utilize a system leakage test in accordance with IWA-5000 in lieu of the hydrostatic test required by Code Case N-504-3. By letter dated May 21, 2009, the licensee requested to withdraw RR 2-ISI-22 application from NRC review (Agencywide Document Access and Management System Accession No. ML091470283) due to the fact that the flaw did not penetrate the pressure boundary during welding operations. | | By letter dated May 18, 2009, the Tennessee Valley Authority, the licensee submitted a relief request (RR) for Browns Ferry Nuclear Power Plant, Unit 2 to the U.S. Nuclear Regulatory Commission (NRC). The proposed RR was to utilize a system leakage test in accordance with IWA-5000 in lieu of the hydrostatic test required by Code Case N-504-3. |
| We acknowledge your request to withdraw the application. | | By letter dated May 21, 2009, the licensee requested to withdraw RR 2-ISI-22 application from NRC review (Agencywide Document Access and Management System Accession No. ML091470283) due to the fact that the flaw did not penetrate the pressure boundary during welding operations. We acknowledge your request to withdraw the application. As a result, NRC staff activities on the review have ceased and the associated Technical Assignment Control Number (No. ME1320) has been closed. |
| As a result, NRC staff activities on the review have ceased and the associated Technical Assignment Control Number (No. ME1320) has been closed. If you have any questions, please contact me at 301-415-2315. | | 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.: 50-260 cc: Distribution via ListServ Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3A Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT UNIT 2 -WITHDRAWAL OF RELIEF REQUEST (2-ISI-22) | | Sincerely, IRA! |
| FOR REPAIR OF CLASSES 1, 2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME1320) | | Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-260 cc: Distribution via ListServ |
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| | Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3A Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801 |
| | |
| | ==SUBJECT:== |
| | BROWNS FERRY NUCLEAR PLANT UNIT 2 - WITHDRAWAL OF RELIEF REQUEST (2-ISI-22) FOR REPAIR OF CLASSES 1, 2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME1320) |
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| ==Dear Mr. Swafford:== | | ==Dear Mr. Swafford:== |
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| By letter dated May 18, 2009, the Tennessee Valley Authority, the licensee submitted a relief request (RR) for Browns Ferry Nuclear Power Plant, Unit 2 to the U.S. Nuclear Regulatory Commission (NRC). The proposed RR was to utilize a system leakage test in accordance with IWA-5000 in lieu of the hydrostatic test required by Code Case N-504-3. By letter dated May 21, 2009, the licensee requested to withdraw RR 2-ISI-22 application from NRC review (Agencywide Document Access and Management System Accession No. ML091470283) due to the fact that the flaw did not penetrate the pressure boundary during welding operations. | | By letter dated May 18, 2009, the Tennessee Valley Authority, the licensee submitted a relief request (RR) for Browns Ferry Nuclear Power Plant, Unit 2 to the U.S. Nuclear Regulatory Commission (NRC). The proposed RR was to utilize a system leakage test in accordance with IWA-5000 in lieu of the hydrostatic test required by Code Case N-504-3. |
| We acknowledge your request to withdraw the application. | | By letter dated May 21, 2009, the licensee requested to withdraw RR 2-ISI-22 application from NRC review (Agencywide Document Access and Management System Accession No. ML091470283) due to the fact that the flaw did not penetrate the pressure boundary during welding operations. We acknowledge your request to withdraw the application. As a result, NRC staff activities on the review have ceased and the associated Technical Assignment Control Number (No. ME1320) has been closed. |
| As a result, NRC staff activities on the review have ceased and the associated Technical Assignment Control Number (No. ME1320) has been closed. If you have any questions, please contact me at 301-415-2315. | | 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.: 50-260 cc: Distribution via ListServ Distribution: | | Sincerely, IRA! |
| PUBLIC RidsNrrPMEBrown RidsAcrsAcnwMailCenter JAdams, EDO LPL2-2 R/F RidsOgcRp VSreenives, NRR JCollins, NRR RidsNrrDorlLpl2-2 RidsNrrDciCpnb RidsRgn2MailCenter RidsNrrLABClayton(hard copy) ADAMS ACCESSION NUMBER' ML091670358 NRR-028 OFFICE LP-WB/PM LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME VSreenivas EBrown BClayton TBoyce DATE 7/1/09 7/1/09 7/1/09 7/1/09 OFFICIAL RECORD COpy}} | | Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-260 cc: Distribution via ListServ Distribution: |
| | PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown RidsOgcRp RidsNrrDciCpnb RidsAcrsAcnwMailCenter VSreenives, NRR RidsRgn2MailCenter JAdams, EDO JCollins, NRR RidsNrrLABClayton(hard copy) |
| | ADAMS ACCESSION NUMBER' ML091670358 NRR-028 OFFICE LP-WB/PM LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME VSreenivas EBrown BClayton TBoyce DATE 7/1/09 7/1/09 7/1/09 7/1/09 OFFICIAL RECORD COpy}} |
Letter Sequence Withdrawal |
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MONTHYEARML0914702832009-05-21021 May 2009 Withdrawal of Proposed Request for Exemption from 10 CFR 50.55a, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Third Ten-Year Inspection Interval - Request for Relief 2-ISI-22 Project stage: Withdrawal ML0916703582009-07-0101 July 2009 Withdrawal of Relief Request (2-ISI-22) for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping Project stage: Withdrawal 2009-05-21
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Category:Code Relief or Alternative
MONTHYEARML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22329A0762022-12-0101 December 2022 Correction of Error in Authorization of Alternative Request BFN-21-ISI-02 ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML18323A1722018-12-31031 December 2018 Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds ML18323A0262018-12-0404 December 2018 Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds ML17261A0362017-10-0606 October 2017 Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds ML17135A1462017-08-18018 August 2017 Browns Ferry Nuclear Plant, Unit 3 - Relief Request No. 3 ISI 29 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Piping Welds (CAC No. MF9258) ML17145A5522017-08-11011 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089) ML17045A7722017-03-14014 March 2017 Browns Ferry Nuclear Plant, Units 2 and 3 - Relief Request 2-ISI-30 and 3-ISI-27 - Relief from ASME Code, Section XI Requirements for Periods of Extended Operation for RPV Circumferential Shell Weld Examinations (CAC Nos. MF7795 and MF7796) ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16020A1152016-02-17017 February 2016 Alternative Relief Request 1-ISI-27 for Relief from the Reactor Vessel Circumferential Weld Examination Requirements of the ASME Code ML12003A0812012-01-20020 January 2012 Safety Evaluation for Relief Request 3-ISI-25, for the Third 10-Year Inservice Inspection Interval ML0921809542009-08-24024 August 2009 Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155 ML0916703582009-07-0101 July 2009 Withdrawal of Relief Request (2-ISI-22) for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ML0912000402009-06-16016 June 2009 Safety Evaluation for Relief Request 2-ISI-18R1 Associated with Inservice Inspection Examination Coverage ML0916104992009-06-12012 June 2009 Verbal Relief Related to Instrument Line Weld Overlay (TAC No. ME1319) (2-ISI-21) ML0913906422009-05-18018 May 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Request for Relief 2-ISI-21, Revision 1 - Examination of Piping Weld Overlays ML0907110772009-04-0202 April 2009 Safety Evaluation for Relief Request 1-ISI-18 Associated with Inspection and Testing of Snubbers ML0833802012008-11-25025 November 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Second Ten-year Inspection Interval - Relief Request for 1-ISI-22 ML0821704212008-07-29029 July 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval- Request for Relief 2-ISI-18, Revision 1 ML0800805242008-05-20020 May 2008 Safety Evaluation for Relief Request 3-ISI-22 Limited Examination Coverage for Valve to Pipe Weld GR-3-63 Tac No. MD6748) ML0725600472007-08-24024 August 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval Requests for Relief 3-ISI-22 & 3-ISI-23 ML0706504752007-02-21021 February 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Second Ten-Year Inspection Interval - Request for Relief 3-ISI-7, Revision 2 ML0700903492007-02-12012 February 2007 Relief Request, Risk-Informed Inservice Inspection of Piping ML0633306482006-12-22022 December 2006 Relief Request, Request for Relief from American Society of Mechanical Engineers, Section XI Requirements for the Third Inservice Inspection Interval - Snubbers ML0631800372006-11-14014 November 2006 Individual Notice, Low Pressure Coolant Injection Loop Crosstie Valve Position Verification ML0615600902006-08-0303 August 2006 Relief Requests, Revision 3-ISI-12 and 3-ISI-19, Associated with Weld Examination Coverage ML0615902822006-07-0303 July 2006 Letter Withdrawal of Relief Requests Regarding Third Interval Inservice Inspection Requirements of the ASME Code ML0613903032006-06-30030 June 2006 Relief, Relief Request 3-ISI-20 Associated with the Use of ASME Code Case- 700 for the Third Inservice Inspection Interval ML0535403782005-12-20020 December 2005 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request to Use Subsequent Edition and Addenda of ASME Section XI Code for Repair and Replacement Activities ML0523101262005-08-18018 August 2005 American Society of Mechanical Engineers RPV Welds Withdrawal of Requests ML0517304872005-08-0202 August 2005 Relief, Inservice Inspection Program Relief Request PDI-4 ML0518106792005-07-18018 July 2005 Safety Evaluation for Request for Relief Regarding the Use of ASME Code Case 700 (TACs MC6437, MC6438) ML0506305582005-03-0404 March 2005 American Society of Mechanical Engineers Section XI, Inservice Inspection Program, Second Ten-Year Inspection Interval - Requests for Relief 3-ISI-7, Revision 1, 3-ISI-12, and 3-ISI-19 ML0502504152005-02-15015 February 2005 Relief, Use of ASME and Pressure Vessel (PV) Code for VT-2 ML0433803212004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, in Service Inspection Program 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. ML0421504382004-10-0606 October 2004 Relief, Relief Request Re. Maximum Allowable Flaw Width When Planar Flaw Evaluation Rules May Be Applied ML0410403752004-04-12012 April 2004 Requests for Relief Nos. 2-ISI-18 and 2-ISI-19 for Third 10-Year Interval Inservice Inspection ML0406200482004-03-0101 March 2004 Brown Ferry, Unit 1, Ltr, Relief, Containment Inservice Inspection ML0404203552004-02-11011 February 2004 Relief, Second 10-Year Interval Inservice Inspection Programs ML0335303822003-12-19019 December 2003 Brown Ferry Nuclear Plant, Units 2 and 3, Relief Request, 2-ISI-21 and 3-ISI-17 to Inservice Inspection Program ML0325909292003-09-12012 September 2003 (BFN) - Unit 1 - American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request for Relief PDI-2 - Clarification and Additional Information ML0316714662003-06-0202 June 2003 Relief, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval - Requests for Relief 2-ISI-18, and 2-ISI-19 ML0314107352003-05-0909 May 2003 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3 -ISI-14, & 3-ISI-15 ML0313500882003-05-0909 May 2003 (Bfn), Unit 3, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3-ISI-14 & 3-ISI-15 2024-06-18
[Table view] 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 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 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 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant 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 IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations 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 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 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 2024-09-03
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 1,2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT UNIT 2 - WITHDRAWAL OF RELIEF REQUEST (2-ISI-22) FOR REPAIR OF CLASSES 1, 2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME1320)
Dear Mr. Swafford:
By letter dated May 18, 2009, the Tennessee Valley Authority, the licensee submitted a relief request (RR) for Browns Ferry Nuclear Power Plant, Unit 2 to the U.S. Nuclear Regulatory Commission (NRC). The proposed RR was to utilize a system leakage test in accordance with IWA-5000 in lieu of the hydrostatic test required by Code Case N-504-3.
By letter dated May 21, 2009, the licensee requested to withdraw RR 2-ISI-22 application from NRC review (Agencywide Document Access and Management System Accession No. ML091470283) due to the fact that the flaw did not penetrate the pressure boundary during welding operations. We acknowledge your request to withdraw the application. As a result, NRC staff activities on the review have ceased and the associated Technical Assignment Control Number (No. ME1320) has been closed.
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.: 50-260 cc: Distribution via ListServ
Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3A Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT UNIT 2 - WITHDRAWAL OF RELIEF REQUEST (2-ISI-22) FOR REPAIR OF CLASSES 1, 2, AND 3 AUSTENITIC STAINLESS STEEL PIPING (TAC NO. ME1320)
Dear Mr. Swafford:
By letter dated May 18, 2009, the Tennessee Valley Authority, the licensee submitted a relief request (RR) for Browns Ferry Nuclear Power Plant, Unit 2 to the U.S. Nuclear Regulatory Commission (NRC). The proposed RR was to utilize a system leakage test in accordance with IWA-5000 in lieu of the hydrostatic test required by Code Case N-504-3.
By letter dated May 21, 2009, the licensee requested to withdraw RR 2-ISI-22 application from NRC review (Agencywide Document Access and Management System Accession No. ML091470283) due to the fact that the flaw did not penetrate the pressure boundary during welding operations. We acknowledge your request to withdraw the application. As a result, NRC staff activities on the review have ceased and the associated Technical Assignment Control Number (No. ME1320) has been closed.
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.: 50-260 cc: Distribution via ListServ Distribution:
PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown RidsOgcRp RidsNrrDciCpnb RidsAcrsAcnwMailCenter VSreenives, NRR RidsRgn2MailCenter JAdams, EDO JCollins, NRR RidsNrrLABClayton(hard copy)
ADAMS ACCESSION NUMBER' ML091670358 NRR-028 OFFICE LP-WB/PM LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME VSreenivas EBrown BClayton TBoyce DATE 7/1/09 7/1/09 7/1/09 7/1/09 OFFICIAL RECORD COpy