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Results
Other: ML040650206, ML040910016, ML041310029, ML042240255, ML042990519, ML051180464, ML051250308, ML060410288, ML060450582, ML060950060, ML061110094, ML061110102, ML061110126, ML061140322, ML061730464, ML091870509, ML11171A037, ML11171A038, ML11308A018
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MONTHYEARML0400603592003-12-31031 December 2003 Letter Transmitting Browns Ferry, Units 1, 2 and 3, Application for Renewed Operating Licenses Project stage: Request ML0406502062004-03-0404 March 2004 Determination of Acceptability and Sufficiency for Docketing and Opportunity for a Hearing Regarding the Application from Tennesssee Valley Authority for Renewal of the Operating Licenses for Browns Ferry, Units 1, 2 & 3 Project stage: Other ML0409100162004-03-31031 March 2004 Review Schedule for Application for Renewal of the Operating Licenses for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Other ML0413100292004-05-0606 May 2004 & 03/31/2004 Summary of Telephone Conferences with Tennesssee Valley Authority Concerning Activities on Browns Ferry Nuclear Plant, Units 1, 2 & 3 LRA Project stage: Other ML0419501002004-06-10010 June 2004 Audit and Review Plan for Plant Aging Management Programs and Reviews - Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Request ML0418101682004-06-28028 June 2004 Summary of Telephone Conference on May 27, 2004, Between the U.S. NRC and the Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 and 3 LRA Project stage: Draft RAI ML0421104852004-07-28028 July 2004 Summary of Telephone Conference Held on July 1, 2004, Between NRC and TVA Concerning Draft Requests for Additional Information (D-RAI) on Browns Ferry Nuclear Plant Units 1, 2,& 3 Project stage: Draft RAI ML0422402552004-08-10010 August 2004 Audit and Review Plan for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plants, Units 1, 2 and 3 Project stage: Other ML0424005502004-08-26026 August 2004 Summary of Telephone Conference Held on July 27, 2004, Between U.S. Nuclear Regulatory Commission & Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 & 3, License Renew Project stage: Draft RAI ML0424502112004-08-31031 August 2004 Summary of Telephone Conference Held on July 12, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) and the Tennessee Valley Authority (TVA) Concerning Requests for Additional Information (RAI) on Browns Ferry Nuclear Plant, Unts 1, Project stage: RAI ML0426005222004-09-16016 September 2004 Summary of Telephone Conference Held on August 19, 2004, Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 & 3 LR Project stage: Draft RAI ML0429905192004-10-21021 October 2004 Summary of Telephone Conference Held on September 22, 2004, Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority Concerning Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA Project stage: Other ML0430905772004-11-0404 November 2004 Request for Additional Information for the Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA (TAC Nos. MC1704, MC1705 and MC1706.) Project stage: RAI ML0430905732004-11-0404 November 2004 Request for Additional Information for the Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA Project stage: RAI ML0511804642005-04-26026 April 2005 Audit and Review Report for Plant Aging Management Programs (Amps) and Aging Management Reviews (Amrs), Browns Ferry Nuclear Plant, Untis 1, 2 and 3 and Memo Project stage: Other ML0512503082005-05-0404 May 2005 Memo, Audit and Review Report for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plant Project stage: Other ML0535603282005-12-20020 December 2005 License Renewal Application - Supplemental Information for the Time Limited Aging Analysis for Stress Relaxation of the Core Plate Hold-Down Bolts and the Unit 1 Periodic Inspection Program (TAC Nos. MC1704. Project stage: Supplement ML0601204532006-01-12012 January 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Tac Nos. MC1704, MC1705, MC1706) Project stage: Approval ML0601103412006-01-12012 January 2006 Transmittal Letter to K. Singer: Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Approval ML0604102882006-01-31031 January 2006 License Renewal Application (LRA) - Annual Update Project stage: Other ML0603302952006-01-31031 January 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1,2, and 3 (TAC Nos. MC1704, MC1705, and MC1706) - Request for Additional Information Related to Appendix F Items in the Application Project stage: Approval ML0604505822006-02-14014 February 2006 License Renewal Application (LRA) - Revised Commitment Tables Project stage: Other ML0606203532006-03-0303 March 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Request for Additional Information Related to Appendix F Items in the Application and the Topics Discussed in the Public Meeting... Project stage: Approval ML0606603742006-03-0707 March 2006 (BFN) Units 1, 2, and 3 License Renewal Application (LRA) - Supplemental Information for the Unit 1 Periodic Inspection (TAC MC1704, MC1705 and MC1706) Project stage: Supplement ML0607903762006-03-0707 March 2006 License Renewal Application (LRA) - Supplemental Information for Open Item 2.4-3 Project stage: Supplement ML0609500602006-04-0404 April 2006 (BFN) - Units 1, 2, and 3 License Renewal Application (LRA) - Unit 1 Lower Drywell Liner Inspections, Unit 1 Periodic Inspection Program, and Residual Heat Removal Service Water Piping Inspections Project stage: Other ML0609701682006-04-21021 April 2006 Transmittal of Supplement 1 to the Safety Evaluation Report (NUREG-1843) - Supplemental Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MC1704, MC1705, MC1706) Project stage: Approval ML0611403222006-04-21021 April 2006 Brown Ferry Units 1, 2, and 3 - License Renewal Application - Revised Commitment List Project stage: Other ML0611401822006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 3 Project stage: Acceptance Review ML0611403522006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 1 Project stage: Acceptance Review ML0609703322006-05-0404 May 2006 Ltr to Karl W. Singer - Issuance of Renewed Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Approval ML0611101022006-05-0404 May 2006 Renewed Facility Operating License DPR-52 Project stage: Other ML0611101262006-05-0404 May 2006 Renewed Facility Operating License No. DPR-68 Project stage: Other ML0611100942006-05-0404 May 2006 Renewed Facility Operating License DPR-33 Project stage: Other ML0611402092006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 2 Project stage: Acceptance Review ML0609703552006-05-0404 May 2006 Federal Register Notice - Notice of Issuance of Renewed Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 for an Additional 20-year Period Project stage: Approval ML0613600442006-06-0707 June 2006 Agenda for Public Meeting with Entergy Operations Incorporated Regarding Spent Fuel Pool Rack Configuration Changes at ANO-1 and ANO-2 on Wednesday 06/07/2006, TAC Nos. MC1704, MC1705 Project stage: Meeting ML0617304642006-06-22022 June 2006 Corrections to Technical Specifications and Renewed Facility Operating License No. DPR-33, for Unit 1 Project stage: Other ML0619102062006-07-0606 July 2006 03/01/2006 - Summary of Meeting with TVA on the License Renewal Application for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Meeting ML0618803982006-07-0606 July 2006 03/09/2006 Summary of a Meeting Held Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority on the License Renewal Application for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Meeting ML0918705092009-07-17017 July 2009 G20090346/LTR-09-0303/EDATS: SECY-2009-0304 - Ltr. Mario Bonaca Report on the Safety Aspects of the License Renewal Application for the National Bureau of Standards Test Reactor Project stage: Other ML11171A0382010-12-31031 December 2010 NEDO-33632, Rev. 0, Browns Ferry (Units 1-3), Core Plate Bolt Analysis Stress Analysis Report. Project stage: Other ML11171A0372011-06-15015 June 2011 BWRVIP-25 Core Plate Bolt Stress Analysis Project stage: Other ML11308A0182011-11-0101 November 2011 One-Time Inspection Procedure, 0-TI-565, Rev. 0003 Project stage: Other 2005-05-04
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Category:Meeting Summary
MONTHYEARML24176A1252024-06-28028 June 2024 Summary of Partially Closed Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request Regarding the Hydrologic Analysis Updates ML24155A0422024-06-13013 June 2024 Meeting Summary: Public Scoping Webinars for the Environmental Review of the Subsequent License Renewal Application for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML24142A5152024-05-28028 May 2024 April 22, 2024, Summary of Public Mtg with Tennessee Valley Authority to Discuss Use of Risk-Informed Process Evaluation for a Proposed License Amendment Request Elimination of Limiting Condition for Operation Actions for the Rod Worth Mini ML24155A0432024-04-18018 April 2024 Meeting Summary ML24089A0712024-04-0101 April 2024 3/20/24 & 3/27/24 2023 TVA Public Annual Assessment Meeting Summary ML24057A0402024-02-27027 February 2024 Summary of February 7, 2024, Public Meeting with Tennessee Valley Authority to Preliminarily Discuss the Planned Approach for the Browns Ferry Nuclear Plant Hydrologic Analysis ML24043A0462024-02-16016 February 2024 Summary of Meeting with TVA to Discuss Use of Risk-Informed Process Evaluation (RIPE) for a Proposed LAR Regarding Elimination of Limiting Condition for Operation Actions for Rod Worth Minimizers ML24008A1592024-01-18018 January 2024 Summary of December 13, 2023, Meeting with Tennessee Valley Authority Regarding a Proposed Change to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23157A1272023-06-13013 June 2023 Meeting Summary for Environmental Pre-Submittal Meeting for Subsequent License Renewal Application on May 11, 2023 ML23142A2132023-05-22022 May 2023 Public Meeting Summary - 2022 Annual Assessment Meetings for Browns Ferry, Sequoyah and Watts Bar Nuclear Plants ML22319A1952022-12-0202 December 2022 Summary of October 13, 2022, Meeting with Tennessee Valley Authority to Discuss Planned Alternative Requests for the Fifth 10-Year Inservice Testing Program Interval for Brown'S Ferry Nuclear Plant, Units 1, 2, and 3 ML22298A1612022-11-17017 November 2022 Summary of Public Meeting on SAMA with TVA ML22266A2742022-09-28028 September 2022 Summary of September 22, 2022, Public Meeting with Tennessee Valley Authority to Discuss a Request to Use a Later Edition of the ASME OM Code ML22108A1842022-04-18018 April 2022 TVA 2021 Annual Assessment Public Meeting Summary ML22103A2472022-04-14014 April 2022 Summary of April 12, 2022, Closed Meeting with Tennessee Valley Authority to Discuss Recently Identified Errors Potentially Affecting the Browns Ferry Revised Criticality Analysis License Amendment Request ML22094A1112022-04-0404 April 2022 Public Meeting Summary 2021 Annual Assessment Meeting Catawba Dockets Nos. 50-413 and 50-414; McGuire No. 50-369 and 50-370; Oconee. 50-269, 50-270, and 50-287 ML22083A0762022-03-24024 March 2022 Summary of March 17, 2022, Closed Meeting with Tennessee Valley Authority to Discuss Recently Identified Errors Potentially Affecting the Browns Ferry Atrium 11 License Amendment Request (EPID L-2021-LLA-0132 ML21291A0092021-11-0303 November 2021 Tennessee Valley Authority Fleet - Summary of October 13, 2021, Teleconference with Tennessee Valley Authority to Discuss Planned License Amendment Requests Related to the Emergency Action Level Scheme ML21266A0532021-10-20020 October 2021 Summary of September 22, 2021, Meeting with Tennessee Valley Authority Regarding Planned License Amendment Request to Adopt Technical Specifications Task Force (TSTF)-205 and TSTF-563 ML21273A1922021-10-12012 October 2021 September 27, 2021, Summary of Meeting with Browns Ferry Nuclear Plant, Units 1 & 2 Related to a Planned Alternative Request Per American Society of Mechanical Engineers (Asmee) Code Case N-526, Alternative Requirements for Successive Sect ML21251A1122021-09-14014 September 2021 Summary of September 7, 2021, Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment ML21165A1482021-06-30030 June 2021 Summary of Closed Meeting with Tennessee Valley Authority to Discuss Planned Requests for Exemption from Certain Requirements of 10 CFR Part 37 ML21155A0212021-06-0808 June 2021 Summary of Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment ML21137A0022021-05-17017 May 2021 Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plants, Docket Nos. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, and 50-391, Meeting Number 20210392 ML20357A0092021-01-19019 January 2021 Summary of December 17, 2020, Teleconference with Tennessee Valley Authority Regarding Planned License Amendment Request Related to Use of Alternate Probability of Detection at Watts Bar Nuclear Plant, Unit 2 ML20175A8012020-08-11011 August 2020 Summary of June 23, 2020, Public Meeting with Tennessee Valley Authority to Discuss a Planned License Amendment ML20162A1532020-06-25025 June 2020 Summary of June 8, 2020, Partially Closed Meeting with Tennessee Valley Authority to Discuss a Planned License Amendment ML20127H8412020-05-0606 May 2020 Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plant, Meeting No. 20200384 ML20094M9012020-04-13013 April 2020 Summary of April 2, 2020 Public Meeting with Tennessee Valley Authority Regarding the Future Submittal of a License Amendment Request Adoption of 10 CFR 50.69 ML19120A2882019-06-0606 June 2019 Summary of March 19, 2019, Closed Meeting with Tennessee Valley Authority a License Amendment Request to Implement Maximum Extended Line Limit Analysis Plus ML19120A3692019-04-30030 April 2019 Public Meeting Summary - Browns Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML18242A4882018-09-24024 September 2018 Summary of Pre-Application Conference Call with Tennessee Valley Authority to Discuss Proposed Changes to Modifications Associated with Approved NFPA 805 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML18101A1012018-04-13013 April 2018 Summary of March 16, 2018, Meeting with Tennessee Valley Authority Regarding a License Amendment Request to Implement Maximum Extended Load Line Limit Analysis Plus for Browns Ferry Nuclear Plant ML18068A0792018-03-15015 March 2018 Summary of Pre-Application Meeting with Tennessee Valley Authority Regarding a Planned License Amendment Request Associated with Modifications to the Control Bay Chillersystems at Browns Ferry Units 1, 2 and 3 ML18053A5362018-03-0101 March 2018 Summary of February 7, 2018, Pre-Application Conference Call with TVA a Planned License Amendment Request to Change the Emergency Response Organization Staffing ML17278A8972017-10-17017 October 2017 Summary of Meeting with TVA Regarding Hydrology-Related Licensing Actions, Browns Ferry, Units 1, 2, and 3, Sequoyah Nuclear, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2(EPID L2016-TOP-0011; CAC Nos. MF8391-MF8397 ML17227A5142017-09-0101 September 2017 Summary of August 1, 2017, Pre-Submittal Public Meeting with TVA Regarding a Class 1E Unbalanced Voltage Relay Licensing Amendment Request for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant ML17131A2512017-05-11011 May 2017 Summary of Public Meeting Concerning Annual Assessment of Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML17061A6722017-04-0606 April 2017 Summary of February 15, 2017, Meeting with Tennessee Valley Authority on Updates to the Transmission System Regarding Extended Power Uprate for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML17017A4552017-02-0303 February 2017 Summary of Meeting with Tennessee Valley Authority Regarding Maximum Extended Load Line Limit Plus Pre-Application Meeting for Browns Ferry Nuclear Plant ML16350A2962016-12-14014 December 2016 Enclosure 3- Reactor Oversight Process Task Force FAQ Log- November 16, 2016 ML16280A2912016-10-31031 October 2016 September 23, 2016, Summary of Public Meeting with TVA Regarding Hydrology-Related Licensing Actions, Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Nuclear Plant, Units 1 & 2 (CAC Nos. MF83 ML16279A2332016-10-0505 October 2016 Summary of Closed Pre-Decisional Enforcement Conference with Tennessee Valley Authority Regarding Browns Ferry Nuclear Plant ML16210A4532016-08-16016 August 2016 07/19/2016 Summary of Meeting with Tennessee Valley Authority Regarding Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant (CAC Nos. MF6741, MF6742, and MF6743) ML16193A4602016-07-21021 July 2016 June 23, 2016, Summary of Closed Meeting with Tennessee Valley Authority Regarding the Structural Adequacy of Steam Dryers for Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (MF6741, MF6742 ML16153A1982016-06-0101 June 2016 2015 EOC Meeting Summary ML16043A2772016-03-14014 March 2016 Summary of Meeting with Tennessee Valley Authority Regarding a License Amendment Request to Modify Browns Ferry Technical Specifications (TS) by Adding New TS 3.3.8.3 (CAC Nos. MF6738, MF6739 and MF6740) ML15321A4942015-11-30030 November 2015 Summary of Public Meeting with Tennessee Valley Authority Regarding the Planned Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant ML15295A2602015-11-0404 November 2015 July 14, 2015, Summary of Public Meeting with Tennessee Valley Authority to Discuss Topics Regarding Seismic Risk Evaluations Related to the Seismic Hazard Reevaluation for Browns Ferry Nuclear Plant (TACs MF3764, MF3765 and MF3766) 2024-06-28
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Text
September 16, 2004 LICENSEE: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Plant Units 1, 2 and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON AUGUST 19, 2004, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND THE TENNESSEE VALLEY AUTHORITY CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION ON BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 LICENSE RENEWAL APPLICATION (TAC NOS. MC1704, MC1705 AND MC1706)
The U.S. Nuclear Regulatory Commission staff and representatives of Tennessee Valley Authority (TVA or the applicant) held a telephone conference on August 19, 2004, to discuss the draft requests for additional information (D-RAIs) related to Section 3.1.2 of the Browns Ferry Nuclear Plant (BFN) license renewal application.
The conference call was useful in clarifying the intent of the staffs questions. On the basis of the discussion, the applicant was able to understand the staff's questions. No staff decisions were made during the telephone conference. In some cases, the applicant agreed to provide information for clarification. contains a listing of the D-RAIs discussed with the applicant, including a description on the status of the items. Enclosure 2 provides a list of the telephone conference participants. The applicant has had an opportunity to comment on this summary.
/RA/
Yoira K. Diaz Sanabria, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos.: 50-259, 50-260 and 50-296
Enclosures:
As stated cc w/encls: See next page
September 16, 2004 LICENSEE: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Plant Units 1, 2 and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON AUGUST 19, 2004, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND THE TENNESSEE VALLEY AUTHORITY CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION ON BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 LICENSE RENEWAL APPLICATION (TAC NOS. MC1704, MC1705 AND MC1706)
The U.S. Nuclear Regulatory Commission staff and representatives of Tennessee Valley Authority (TVA or the applicant) held a telephone conference on August 19, 2004, to discuss the draft requests for additional information (D-RAIs) related to Section 3.1.2 of the Browns Ferry Nuclear Plant (BFN) license renewal application.
The conference call was useful in clarifying the intent of the staffs questions. On the basis of the discussion, the applicant was able to understand the staff's questions. No staff decisions were made during the telephone conference. In some cases, the applicant agreed to provide information for clarification. contains a listing of the D-RAIs discussed with the applicant, including a description on the status of the items. Enclosure 2 provides a list of the telephone conference participants. The applicant has had an opportunity to comment on this summary.
/RA/
Yoira K. Diaz Sanabria, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos.: 50-259, 50-260 and 50-296
Enclosures:
As stated cc w/encls: See next page Accession No.: ML042600522 DISTRIBUTION:
See next page Document Name:C:\ORPCheckout\FileNET\ML042600522.wpd OFFICE PM:RLEP LA:RLEP SC:RLEP NAME Y. Diaz-Sanabria M. Jenkins S. Lee DATE 9/15/04 9/15/04 9/16/04 OFFICIAL RECORD COPY
DISTRIBUTION: Dated: September 16, 2004 Accession No: ML042600522 HARD COPY RLEP RF Yoira Diaz Sanabria (PM)
E-MAIL:
RidsNrrDSSA RidsNrrDe RLEP staff S. Black Y.L. (Renee) Li C. Li K. Jabbour A. Hodgdon R. Weisman C. Carpenter A. Howe R. Subbaratnam G. Cranston G. Cheruvenki B. Elliot
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 LICENSE RENEWAL APPLICATION DRAFT REQUEST FOR ADDITIONAL INFORMATION (D-RAI)
AGING MANAGEMENT OF REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM SECTIONS 3.1.2 Reactor Vessel Internals Core Shroud and Core Plate D-RAI-3.1.2.1-6 Table 3.1.2.1 (a) According to Section IV-B.1.1-d/B1.1.4 of NUREG-1801, augmented inspection of access hole covers is required for Alloy 600 materials and Alloy 182 welds. The applicant should provide details on the type and frequency of inspection of the access hole covers.
(b) According to Section IV-B.1.1-d of NUREG-1801, irradiation assisted stress corrosion cracking is an aging effect for core shroud components. Please provide an explanation for excluding this aging mechanism in Table 3.1.2.1. Provide details of the AMP that will be implemented on this system.
(c) Describe plant-specific experience related to IGSCC cracking of the stainless steel and Inconel components in the core shroud, and shroud support access hole covers. Provide details on any occurrence of IGSCC cracking, and the effective AMP that will be implemented on these systems at BFN Units.
(d) The applicant should address the plant-specific experience on sudden increase in RCS water conductivity due to a leak in condensate and or reactor water clean up systems. Provide information on the impact of sudden increase in RCS water conductivity on IGSCC of core shroud welds.
(e) Provide information on verification methods to monitor the effectiveness of the hydrogen water chemistry program. Explain the methodology of ensuring hydrogen availability in the core shroud region. If ECP probes are not used to monitor availability of hydrogen, explain the validity of using secondary parameters (i.e., main steam/feedwater oxygen levels) to assess the hydrogen availability at core shroud welds.
Discussion: The applicant indicated that the question is clear. This question will be sent as RAI 3.1.2.1-6.
Enclosure 1
Core Spray Spargers and piping D-RAI-3.1.2.2-7 Table 3.1.2.2 (a) According to the Section IV-B.1.3-a of NUREG-1801, irradiation assisted stress corrosion cracking is an aging effect for the core spray lines and spargers components. Please provide an explanation for excluding this aging effect in Table 3.1.2.1. Provide details of the AMP that will be implemented on this system.
(b) Core Spray piping and spargers contain crevice conditions in some weld areas. Explain the methodology of ensuring hydrogen availability in these systems. Since the presence of crevice conditions enhances the occurrence of IGSCC, the applicant should provide details on the type and extent of inspections to identify IGSCC, and the mitigation techniques at BFN Units 2 and 3.
Discussion: The applicant indicated that the question is clear. This question will be sent as RAI 3.1.2.2-7.
Reactor Vessel Internals Dry Tube and Guide Tube D-RAI-3.1.2.2-8 Table 3.1.2.2 (a) According to Section IV-B.1.6-a of NUREG-1801, irradiation assisted stress corrosion cracking is an aging effect for dry tube and guide tube components. Please provide an explanation for excluding this aging effect in Table 3.1.2.1. Provide information on the AMP that will be implemented on this system.
(b) The AMP for the dry tube and guide tube components addressed in the application references BWRVIP-47. Table 3.1-2 of BWRVIP-47 indicates that some of the incore housing guide tubes and dry tubes for BFN Units 2 and 3 experienced cracking and were subsequently replaced with materials resistant to cracking. Provide information on the type and grade of the replaced material, and its performance at BFN Units 2 and 3. The staff requests additional information on the type and extent of subsequent inspections of the dry tubes and guide tubes for BFN Units 2 and 3. The applicant should also address any existence of cracks in BFN Unit 1 dry tubes and guide tubes. Identify the method and frequency of inspection of the BFN Unit 1 dry tubes and guide tubes. Provide information on any mitigating techniques that will be implemented to reduce the susceptibility to cracking in Unit 1 dry tubes and guide tubes.
(c) According to Section 2.2.1.2 of BWRVIP-47, furnace-sensitized stainless steel stub tubes are more susceptible to IGSCC. The applicant should provide information on any existing furnace-sensitized stub tubes at BFN Units. Provide details on the AMP that will be implemented for the furnace-sensitized stainless steel stub tubes at the BFN Units. Identify whether any furnace-sensitized stainless steel stub tubes have previously experienced cracking due to SCC, IGSCC or cyclic loading, and the extent of the cracking. Identify the method and frequency of inspection.
(d) According to the Section 2.2.1.2 of BWRVIP-47, weld metal 182 is more susceptible to IGSCC. Provide details on the AMP for components that have 182 weld metal in these systems at BFN Units. Identify whether any 182 weld metals have previously experienced cracking due to SCC, IGSCC or cyclic loading, and the extent of cracking. Identify the method and frequency of inspection.
Discussion: The applicant indicated that the question is clear. This question will be sent as RAI 3.1.2.2-8.
Jet Pump Assembly D-RAI-3.1.2.2-9 Table 3.1.2.2 Provide information on any existing Cast Austenitic Stainless Steel (CASS) jet pump components. The applicant should provide the information on the jet pump components:
(a) Information on type of casting (i.e; centrifugal or static)
(b) The composition of CASS (i.e; Molybdenum content and delta ferrite values)
(c) Previous plant-specific experience regarding the cracked components and type and extent of subsequent inspection of CASS jet pump components due to neutron and thermal embrittlement. The fluence values should be based on the end of the extended period of operation and power uprate.
(d) The LRA should address any technical specification changes related to jet pump components.
Discussion: The applicant indicated that the question is clear. This question will be sent as RAI 3.1.2.2-9.
Top Guide D-RAI-3.1.2.2-10 Table 3.1.2.2 According to Section IV -B.1.2-a of NUREG-1801, irradiation assisted stress corrosion cracking is an aging effect for top guide components. Please provide explanation for excluding this issue in Table 3.1.2.1. Provide details on the AMP that will be implemented on this system.
Discussion: The applicant indicated that the question is clear. This question will be sent as RAI 3.1.2.2-10.
Reactor Pressure Vessel (RPV) Vents and Drains Piping D-RAI 3.1.2.3-2 The LRA should identify aging effects for the carbon steel drain line penetrations exposed to reactor coolant water up to 288°C (550° F). Such drain lines are likely to experience loss of material due to corrosion. This assessment is consistent with Item D2.1-a, Chapter V.D2 of NUREG-1801. Explain why loss of material due to corrosion is not considered as an aging effect for these components, or provide a program for managing such effect.
Table 3.1.2.3 -RPV Vents and Drains, identifies a one-time inspection specified in B.2.1.29 as a part of the AMP. According to B.2.1.29 a one time inspection is applicable for piping and fittings with diameter less than 4 inches Nominal Pipe Size (NPS). Identify whether the reactor vents and drain systems have previously experienced cracking due to SCC, IGSCC or cyclic loading, and the extent of cracking. Identify the method of the one-time inspection. The LRA does not address the type and the frequency of the inspection requirements as a part of the AMP, for piping greater than 4 inches NPS.
Discussion: The applicant indicated that the question is clear. This question will be sent as RAI 3.1.2.3-2.
Reactor Recirculation System Piping D-RAI 3.1.2.4-2 Table 3.1.2.4 identifies a one-time inspection specified in B.2.1.29 as a part of the AMP.
According to B.2.1.29 one-time inspection is applicable for piping and fittings with diameter less than 4 inches NPS. Identify whether the reactor recirculation system has previously experienced cracking due to SCC, IGSCC or cyclic loading, and the extent of cracking. Identify the method of the one time inspection. The LRA does not address the type and frequency of the inspection requirements as a part of the AMP, for piping greater than 4 inches NPS.
Discussion: The applicant indicated that the question is clear. This question will be sent as RAI 3.1.2.4-2.
LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE ON DRAFT REQUESTS FOR ADDITIONAL INFORMATION August 19, 2004 Participants Affiliation Yoira Diaz U.S. Nuclear Regulatory Commission (NRC)
Barry Elliot NRC Ganesh Cheruvenki NRC Ram Subbaratnam NRC Gregory Cranston NRC Ken Brune Tennessee Valley Authority (TVA)
Valarie Smith TVA Terry Knuettel TVA Mickey Hamby TVA Enclosure 2
BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Karl W. Singer, Senior Vice President Mr. Robert G. Jones Nuclear Operations Browns Ferry Unit 1 Plant Restart Manager 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 E. Maddox, Vice President Mr. Mark J. Burzynski, Manager Engineering & Technical Services Nuclear Licensing Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place 4X Blue Ridge 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Ashok S. Bhatnagar, Site Vice President Mr. Timothy E. Abney, Manager Browns Ferry Nuclear Plant Licensing and Industry Affairs Tennessee Valley Authority Browns Ferry Nuclear Plant P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 P.O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority Mr. Bobby L. Holbrook ET 11A Senior Resident Inspector 400 West Summit Hill Drive U.S. Nuclear Regulatory Commission Knoxville, TN 37902 Browns Ferry Nuclear Plant 10833 Shaw Road Mr. Thomas J. Niessen, Acting General Athens, AL 35611 Manager Nuclear Assurance State Health Officer Tennessee Valley Authority Alabama Dept. of Public Health 6A Lookout Place RSA Tower - Administration 1101 Market Street Suite 1552 Chattanooga, TN 37402-2801 P.O. Box 303017 Montgomery, AL 36130-3017 Mr. Michael D. Skaggs Plant Manager Browns Ferry Nuclear Plant Chairman Tennessee Valley Authority Limestone County Commission P.O. Box 2000 310 West Washington Street Decatur, AL 35609 Athens, AL 35611 Mr. Jon R. Rupert, Vice President Mr. Fred Emerson Browns Ferry Unit 1 Restart Nuclear Energy Institute Browns Ferry Nuclear Plant 1776 I St., NW, Suite 400 Tennessee Valley Authority Washington, DC 20006-2708 P.O. Box 2000 Decatur, AL 35609