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MONTHYEARML13227A3532013-04-17017 April 2013 Transmittal of Technical Report 3002000078, BWRVIP-271NP: BWR Vessel & Internals Project Testing and Evaluation of the Browns Ferry Unit 2 120 Degrees Capsule Project stage: Request ML13227A1032013-08-14014 August 2013 License Amendment Request Under Exigent Circumstances for the Administrative Change to Remove the Notes on Technical Specification Figures 3.4.9-1 and 3.4.9-2 Project stage: Request ML13232A3922013-08-16016 August 2013 NRR E-mail Capture - Browns Ferry, Unit 1 Exigent Amendment - Administrative Changes to Remove the Notes on TS Figures 3.4.9-1 and 3.4.9-2 (P-T Curves) (TAC No. MF2564) - Request for Additional Information (RAI) Project stage: RAI ML13231A0852013-08-16016 August 2013 NRR E-mail Capture - Browns Ferry, Unit 1 Exigent Amendment - Administrative Changes to Remove the Notes on TS Figures 3.4.9-1 and 3.4.9-2 (P-T Curves) (TAC No. MF2564) - Acceptance Review Project stage: Acceptance Review ML13227A2552013-08-16016 August 2013 Individual Fr Notice of Appliaction and Amendment to Facility Operating License Project stage: Other ML13227A2532013-08-16016 August 2013 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity of a Hearing Project stage: Other NRC-2013-0198, Individual Fr Notice of Appliaction and Amendment to Facility Operating License2013-08-16016 August 2013 Individual Fr Notice of Appliaction and Amendment to Facility Operating License Project stage: Other ML13235A3082013-08-21021 August 2013 Tennessee Valley Authority Response to Request for Additional Information Regarding License Amendment Request Under Exigent Circumstances for the Administrative Change to Remove the Notes on Technical Specification Figures 3.4.9-1 and 3.4.9 Project stage: Response to RAI ML13256A3792013-09-0303 September 2013 NRR E-mail Capture - Browns Ferry Unit Exigent Amendment Additional RAI Project stage: Other ML13252A3382013-09-0606 September 2013 Tennessee Valley Authority Response to Request for Additional Information Regarding License Amendment Request Under Exigent Circumstances for the Administrative Change to Remove the Notes on Technical Specification Figures 3.4.9-1 and 3.4.9 Project stage: Response to RAI ML13254A0812013-09-13013 September 2013 Issuance of Amendment Under Exigent Circumstances to Remove Notes from Technical Specifications 3.4.9-1 and 3.4.9-2 Project stage: Approval 2013-08-21
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 August 21, 2013 10 CFR 50.90 10 CFR 50.91 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
Tennessee Valley Authority Response to Request for Additional Information Regarding License Amendment Request Under Exigent Circumstances for the Administrative Change to Remove the Notes on Technical Specification Figures 3.4.9-1 and 3.4.9-2
References:
- 1. Letter from TVA to NRC, "License Amendment Request under Exigent Circumstances for the Administrative Change to Remove the Notes on Technical Specification Figures 3.4.9-1 and 3.4.9-2," dated August 14, 2013
- 2. Electronic Mail from NRC to TVA, "Request for Additional Information Regarding Tennessee Valley Authority's License Amendment Request Under Exigent Circumstances for the Administrative Change to Remove the Notes on Technical Specification Figures 3.4.9-1 And 3.4.9-2 for Browns Ferry Nuclear Plant, Unit 1 Docket No. 50-259 (TAC No. MF2564)," dated August 16, 2013 (ML13232A392)
On August 14, 2013, Tennessee Valley Authority (TVA) submitted an application under exigent circumstances (Reference 1) to the Nuclear Regulatory Commission (NRC) to remove the Notes from the Browns Ferry Nuclear Plant, Unit 1 Technical Specification Figures 3.4.9-1 and 3.4.9-2 in accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.90. By NRC email dated August 16, 2013 (Reference 2), the NRC forwarded to TVA a Request for Additional Information (RAI) regarding the Reference 1 submittal. Due to the exigent nature of the TVA request for a license amendment, the response was requested to be provided as soon as possible.
D 3 tedonrecycled paper Prin
U. S. Nuclear Regulatory Commission Page 2 August 21, 2013 to this letter provides the TVA response to the NRC RAI.
There are no regulatory commitments associated with this transmittal. Please direct any questions concerning this matter to Mr. Edward D. Schrull at (423) 751-3850.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 21st day of August 2013.
Respec J. .Shea ce President Nuclear Licensing
Enclosure:
TVA Response to NRC Request for Additional Information cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health
ENCLOSURE TVA Response to NRC Request for Additional Information NRC Request for Additional Information (RAI) Question I In the LAR, TVA refers to the non-proprietaryreport, NEDO-33112, "Pressure-Temperature Curves for TVA Browns Ferry Unit 1" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML043440231), for a description of the fluence calculations.
The first paragraphof Section 1.0, "Introduction,"of NEDO-33112 states, "This report incorporatesa fluence calculated in accordancewith the GE Licensing Topical Report NEDC-32983P, which has been approvedby the NRC in a SER [14], and is in compliance with Regulatory Guide 1.190. This fluence represents an Extended Power Uprate (EPU)for the ratedpower of 3952 MWt."
Verify whether the 3,952 MWt power level was assumed for the entire 16 effective full power years (EFPY)exposure period for BFN-1, and verify that NEDC-32983Pwas the only method used to determine the reactorvessel neutron fluence over the 16 EFPY operatingperiod for BFN-1.
TVA Response Tennessee Valley Authority (TVA) verifies that the Extended Power Uprate (EPU) power level of 3952 MWt was assumed for the entire 16 effective full power years (EFPY) exposure period for Browns Ferry Nuclear Plant (BFN), Unit 1 as presented in NEDO-33112.
TVA also verifies that the method employed in NEDC-32983P was the only method used to determine the reactor vessel neutron fluence over the 16 EFPY operating period for BFN, Unit 1.
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NRC Request for Additional Information (RAI) Question 2 Section IV of Appendix H, "ReactorVessel Material Surveillance Program Requirements," to Title 10 of the Code of FederalRegulations (10 CFR) Part50, "DomesticLicensing of Production and Utilization Facilities,"specifies requirements for reporting of test results for capsules withdrawn from the reactorpressure vessel (RPV) in accordance with an approved RPV materials surveillance program. Those requirementsspecify that summary test reportsare due within one year after the date of capsule withdrawal unless an extension is granted by the Director,Office of Nuclear ReactorRegulation (NRR), and if a change in the Technical Specificationsis required, eitherin the pressure-temperature(P-T) limits or in the operating proceduresrequired to meet the limits, the expected date for submittal of the revised Technical Specificationsmust be provided with the report. NRC is aware that a capsule was removed for testing from BFN Unit 2 in February 2010, and a summary test reportis available as EPRI Technical Report 3002000078, "BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry Unit 2 1200 Capsule,"April 2013 (ADAMS Accession No.
ML13227A353). NRC is also aware that the test results from the BFN Unit 2 1200 capsule are applicableto BFN-1 per the Boiling Water Reactor Vessel and Internals Project (B WR VIP)
IntegratedSurveillance Program (ISP), as documented in EPRI Technical Report 1025144NP, "BWRVIP-86NP, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan," May 2013 (ADAMS Accession No.
ML13176A097).
Provide an evaluation of the impact of the BFN Unit 2 1200 capsule test results on the 16 EFPY P-T curves for BFN-1 included in TVA's LAR.
TVA Response The BFN, Unit 2 1200 surveillance capsule was removed for testing in March 2011 during BFN, Unit 2 Refueling Outage 16. The Electric Power Research Institute (EPRI) / Boiling Water Reactor Vessel and Internals Project (BWRVIP) provided results to TVA from the evaluation of the BFN, Unit 2 1200 capsule surveillance data on April 10, 2013. These results were also provided separately to the NRC by the BWRVIP in accordance with 10 CFR 50, Appendix H. In accordance with the reporting requirements of 10 CFR 50, Appendix H and BWRVIP-1 35, "ISP Data Source Book and Plant Evaluations," Revision 1, September 2007, if the Pressure-Temperature (P-T) limits curves are determined to be non-conservative after consideration of this new data, TVA is required to notify the NRC and submit updated P-T limits curves to the NRC within one year following receipt of this information (i.e., by April 10, 2014). BFN has initiated Problem Evaluation Report (PER) 750662 to provide for review of the data and to determine the effects, if any, on plant P-T limits curves and leak test temperatures. Upon completion of the review, if P-T limits curves are determined to be non-conservative, TVA will notify the NRC of any required changes to the P-T limits curves in accordance with 10 CFR 50 Appendix H.
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