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MONTHYEARML11353A3192011-12-13013 December 2011 12/8/11 Meeting Slides - Brown Ferry Nuclear Plant, Units 1, 2, and 3 - Meeting with the Tennessee Valley Authority (TVA) to Discuss Delay in Submittal of Fire Risk Reduction Amendment Request Project stage: Meeting ML12017A1862012-01-13013 January 2012 Revised Submittal Schedule for License Amendment Request to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition Project stage: Request ML12053A0192012-02-17017 February 2012 Additional Planned Fire Risk Reduction Modifications Project stage: Request ML12055A0632012-02-24024 February 2012 Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) Regarding Fire Protection Project stage: Request ML12066A1962012-03-0909 March 2012 National Fire Protection Association (NFPA) -805 License Amendment Request Delay Project stage: Other ML12083A1982012-03-20020 March 2012 Request for Extension of Enforcement Discretion Regarding Transition to National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition Project stage: Request ML12053A1882012-05-18018 May 2012 Plants, Units 1, 2, and 3 - Letter - Confirmatory Order (Effective Immediately) (TAC Nos. ME7841, ME7842, and ME7843) Project stage: Other ML12053A1902012-05-18018 May 2012 Federal Register Notice - Confirmatory Order Modifying License (Effective Immediately) Project stage: Other ML12171A3632012-06-28028 June 2012 Summary of Meeting with Tennessee Valley Authority to Discuss the National Fire Protection Association - 805 Transition for Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Meeting ML12240A0802012-09-10010 September 2012 10/3/2012 Notice of Forthcoming Meeting with Tennessee Valley Authority Regarding Voluntary Fire Protection Risk Initiative Project stage: Request ML12272A0612012-09-28028 September 2012 11/8/12 Notice of Forthcoming Meeting with Tennessee Valley Authority Regarding Voluntary Fire Protection Risk Initiative for Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Request ML12324A3352012-11-0808 November 2012 11/8/12 Meeting Slides Regarding Browns Ferry Nuclear Plant Risk Reduction and NFPA 805 Transition Update Project stage: Meeting ML12324A3322012-11-30030 November 2012 11/8/12 Summary of Meeting with Tennessee Valley Authority to Discuss the NFPA-805 Transition for Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Meeting 2012-02-24
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Category:Graphics incl Charts and Tables
MONTHYEARML21286A5422021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.5, Analyses of Abnormal Operational Transients ML21286A3972021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.12, Process Radiation Monitoring Systems Characteristics ML21286A3422021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.9, Reactor Water Cleanup System Equipment Design Data ML21286A3592021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 6, Table 6.4, (Deleted by Amendment 13) ML21286A3762021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.1, Systems (or Portions of Systems) Required to Mitigate LOCA And/Or HELB ML21286A3732021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.2, Reactor Protection System Instrumentation Specifications ML21286A3682021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.3, Primary Containment Isolation ML21286A3892021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.7, Reactor Manual Control System Instrumentation ML21286A3952021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.6, Refueling Interlocks Effectiveness ML21286A5662021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.13-1, Results of BFN Atwsi Evaluation ML21286A5522021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.5, Analyses of Abnormal Operational Transients ML21286A5502021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.4, Approach to Safety Analysis ML21286A5482021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.6, Iodine-131 Activity (Ci) by Location as Function of Time for CRDA ML21286A5432021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 13, Table 13.5, Startup and Power Test Program ML21286A4042021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.13, Area Radiation Monitoring ML21286A5322021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.6, Analysis of Design Basis Accidents ML21286A5282021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.4, Approach to Safety Analysis ML21286A5162021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 10, Table 10.17, Process Sampling Systems ML21286A4942021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 10, Table 10.11, Power Block Structures ML21286A4602021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 10, Table 10.4, Tools and Servicing Equipment ML21286A4572021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 12, Table 12.2, Reactor Building Concrete Structure Base Slab Design Data ML21286A4522021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 12, Table 12.3, Plant Radiation Zone Classification ML21286A4272021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 8, Table 8.4, Normal Auxiliary Power ML21286A4242021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 8, Table 8.6, 250-V DC Power Supply ML21286A4232021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.20, Design Output Documents ML21286A4142021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 8, Table 8.5, Standby AC Power Supply ML21286A4092021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.16, Process Computer System ML21286A2772021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table 2.3, Meteorology ML21286A2232021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G, State B ML21286A2222021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G - BWR Operating States ML21286A2262021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G, State D ML21286A2272021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G, State a ML21286A2622021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Table 1.11, Id Resolution of Construction Permit Concern - Summary ML21286A2522021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Table 1.4-1, Class of BWR Systems Criteria Requirements for Safety Evaluation ML21286A2662021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table 2.5, Sheets 1-3, Historical Earthquake Listing 200 Mile Radius Around 87.11 W Lon 34/71 N Lat ML21286A3172021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.3, Reactor Recirculation System ML21286A2002021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix a, AEC General Design Criteria - Group 1 (Overall Plant Requirements) ML21286A2722021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Table 1.7, Comparison of Nuclear System Design Characteristics ML21286A3482021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 6, Table 6.5, Plant Parameters Used Locaa Analysis ML21286A3542021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 6, Table 6.3, Emergency Core Cooling Systems Equipment Design Data Summary ML21286A3672021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.5, Neutron Monitoring System, SRM Trips ML21286A3962021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.8, Reactor Vessel Instrumentation ML21286A3122021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 3, Table 3.2-1, Deleted by Amendment No. 16 ML21286A3132021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 3, Table 3.3, Reactor Vessel Internals, Mechanical Design Data ML21286A2962021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.2, Reactor Pressure Vessel Materials ML21286A2822021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table 2.4A, Maximum Possible Flood ML21286A2842021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table, 2.4, Deleted ML21286A3112021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.4, Nuclear Steam Pressure Relief System ML21286A3242021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 3, Table 3.6, Definition of Fuel Design Limits ML21286A3432021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.8, Residual Heat Removal System Equipment Design Data 2021-10-04
[Table view] 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
[Table view] Category:Schedule and Calendars
MONTHYEARCNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal ML23138A2522023-05-18018 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections ML15282A2412015-09-21021 September 2015 List and Status of Plant Modifications NL-15-169, Browns Ferry, Units 1, 2, and 3, List and Status of Plant Modifications2015-09-21021 September 2015 Browns Ferry, Units 1, 2, and 3, List and Status of Plant Modifications ML13193A0172013-07-0808 July 2013 Response to NRC Regulatory Issue Summary 2013-06, Preparation and Scheduling of Operator Licensing Examinations ML12307A1042012-10-29029 October 2012 Tennessee Valley Authority - Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML12083A1982012-03-20020 March 2012 Request for Extension of Enforcement Discretion Regarding Transition to National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition ML0823301832008-08-15015 August 2008 Reply to NRC Regulatory Issue Summary (RIS) 2008-16, Preparation and Scheduling of Operator Licensing Examinations ML0707203842007-03-0707 March 2007 Restart Ip&S Report ML0632101102006-11-0707 November 2006 Restart Inspection Plan and Schedule (Ip&S) Report - Enclosure 2 ML0630000072006-10-20020 October 2006 Encl 2: BF1 Restart Master Tracking Forecast Schedule ML0703800342006-02-0606 February 2006 Restart Inspection Plan and Schedule (Ip&S) Report 2023-06-06
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 March 20, 2012 10 CFR 50.4 10 CFR 50.48 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Request for Extension of Enforcement Discretion Regarding Transition to National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, for Browns Ferry Nuclear Plant Units 1, 2, and 3,
References:
- 1. Letter from TVA to NRC, "Browns Ferry Nuclear Plant (BFN) - Units 1, 2, and 3 - Letter of Intent to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition," dated March 4, 2009.
- 2. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, And 3
- Response to Letter of Intent to Adopt Title 10 of The Code of Federal Regulations, Part 50, Section 48(c)," dated September 17, 2009
- 3. Letter from TVA to NRC, "Revised Submittal Schedule for License Amendment Request to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, for Browns Ferry Nuclear Plant Units 1, 2, and 3," dated January 13, 2012.
- 4. Letter from TVA to NRC, "Additional Planned Fire Risk Reduction Modifications for Browns Ferry Nuclear Plant Units 1, 2, and 3," dated February 17, 2012.
- 5. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3
- National Fire Protection Association (NFPA) - 805 License Amendment Request Delay," dated March 9, 2012. ,OL42
U.S. Nuclear Regulatory Commission Page 2 March 20, 2012 By letter dated March 4, 2009 (Reference 1), the Tennessee Valley Authority (TVA) informed the NRC of plans to submit a license amendment request to adopt National Fire Protection Association Standard 805 (NFPA Standard 805), Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition within approximately three years of the reference letter. By letter dated September 17, 2009 (Reference 2), the NRC acknowledged TVA's intent to transition Browns Ferry Nuclear Plant (BFN) Units 1, 2 and 3 to NFPA 805 and in accordance with the NRC's Interim Enforcement Policy granted BFN Enforcement Discretion for Certain Fire Protection Issues for a period of three years beginning on March 4, 2009.
At a public meeting between the NRC staff and TVA representatives on December 8, 2011, TVA described the strategy it has pursued of performing modifications to the BFN and its associated procedures in parallel with development of a license amendment request to adopt NFPA Standard 805. The objective of the parallel approach has been to achieve meaningful reduction in fire risk at BFN while simultaneously pursuing the regulatory basis provided by NFPA Standard 805. TVA has completed several key modifications to the facility that have improved risk and reduced the number of time critical operator manual actions required to implement the current safe shutdown fire strategy.
As a follow-up to the December 8, 2011, public meeting, in letter dated January 13, 2012 (Reference 3), TVA informed the NRC that the schedule for submitting an application to adopt the NFPA Standard 805 for BFN had been revised to no later than March 29, 2013. Additionally, TVA provided a list of completed modifications and a list of additional planned modifications and associated implementation schedules in February 17, 2012, letter (Reference 4). In a public teleconference held on February 29, 2012, TVA further outlined the reasons for the proposed revision to the NFPA 805 application submittal date and major activities that need to be completed in support of the submittal.
By letter dated March 9, 2012 (Reference 5), the NRC requested that TVA provide additional information to justify the revised license amendment submittal date. This response provides the requested additional information. Additionally, TVA will ensure that the following information is available for NRC review:
- 1. Listing of all fire protection-relatednoncompliances and the related compensatory measures for those noncompliances.
- 2. Documentation ensuring each OperatorManualAction put in place as a compensatory measure is feasible and reliable, in accordancewith the guidance in Regulatory Issue 2005-07, "CompensatoryMeasures to Satisfy the Fire ProtectionProgramRequirements",
- and,
- 3. A description of the physical modificationsperformed, if any, to addressexisting fire protection issues and noncompliances.
U.S. Nuclear Regulatory Commission Page 3 March 20, 2012 The enclosure to this letter contains a table which provides the status and completion schedule, as of March 14, 2012, for the remaining key activities and major milestones for completing TVA's license amendment request. The targeted completion dates in the enclosure were established to provide schedule margin to ensure TVA meets the March 29, 2013 commitment to submit an NFPA 805 license amendment request.
Section 9.1 of the NRC Interim Enforcement Policy states in part that enforcement discretion may apply to noncompliances identified during the licensee transition process. This timeframe starts on the date as specified in the licensee's letter of intent to transition to 10 CFR 50.48(c) and ends (1) 3 years after that initial start date or (2) on the date as specified in the licensee's commitment letter, as amended and approved by the NRC. Additionally, SECY-12-0031 provides the NRC Staff position that enforcement discretion could be extended if the licensee provides adequate justification. In evaluating the justification provided by a licensee, the staff would consider, but not be limited by, the status of the industry peer review, plant modifications, and the licensee's compliance reviews.
TVA has made significant progress in several key areas of the NFPA Standard 805 transition project. The initial PRA peer review has been completed. In the area of Fundamental Fire Protection Program Review, all 14 NFPA Code Compliance Evaluations are either complete or in review. For Nuclear Safety Capability Assessment, the Safe Shutdown Equipment List and Safe Shutdown Circuit Analysis have been issued for review. The circuit analysis for Non Power Operations components has been completed. Additional details are provided in the enclosure. TVA is requesting extension of Enforcement Discretion for Certain Fire Protection Issues during the period of transition to National Fire Protection Association (NFPA) 805 for BFN Units 1, 2 and 3 until March 29, 2013.
If you have any question on these matters, please contact me at 423-718-9576.
There are no new commitments contained in this letter.
Resp ully, r
u cl g eLicensing orate Nuclear
Enclosure:
Status and Schedule of Major NFPA 805 Milestones
U.S. Nuclear Regulatory Commission Page 4 March 20, 2012 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 Request for Extension of Enforcement Discretion Regarding Transition to National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition for Browns Ferry Nuclear Plant Units 1, 2, and 3, Status and Schedule of Major NFPA 805 Milestones
Enclosure Status and Schedule of Major NFPA 805 Milestones (as of March 14, 2012) runaameniai ri-i Classical Fire Protection Transition Program Review 6 - Complete NFPA Code Compliance 15-Jan-10 04-Jun-12 7 - Final Review 14 total code compliance evaluations Evaluation 1 - Draft Issued for required Review Reviewing and Existing Equivalency Evaluation 01-Feb-10 20-Apr-12 Incorporating Transition Comments Final Owner Review Fire Area Licensing Action Review 02-Nov-09 28-Mar-12 Complete - Vendor Report has been issued for comment.
Nuclear Safety Capability Nuclear Safety Performance Assessment (NSCA) Criteria Transition SSEL and Logic Review and Upgrade Safe Review and Upgrade Shutdown Equipment List (SSEL) 14-Dec-09 14-May-12 Complete - Draft and Logics Calculation issued for Review SSD Circuit Analysis Review and Upgrade Safe 12-Mar-10 11-Apr-12 Complete - Draft Shutdown (SSD)Circuit Analysis Calculation issued for review Pass 1a was started to facilitate parallel path activities - initial fire area 43 of 43 Fire Areas assessments were conducted while Complete cable routing and circuit analysis was still in development to identify and address generic/high level issues 2 of 43 Fire Areas in 15 Pass lb is the completed fire area Fire Area Assessment - Pass 1 b 23-Feb-12 28-Jun-12 Progress assessment input to the Fire Risk Evaluations (FREs)
Pass 2 is final pass after FREs are 15-May-12 02-Aug-12 Not Started Plete Fire Area Assessment - Pass 2 II I Icomplete E-1
Enclosure Status and Schedule of Major NFPA 805 Milestones (as of March 14, 2012) inl11lal iMuflO~~iation Scope Identified (see See February 17, 2012 letter to NRC comments) -
NFPA 805 Modification Scoping 03-Nov-i 1 04-Oct-12 for modifications committed to be Additional Scope will implemented proactively be Determined upon Completion of FREs Non-Power Operational (NPO) Non-Power Operational Modes Modes Transition Transition Perform Circuit Analysis for NPO 18-Nov-10 19-Mar-12 Complete Components In Progress - Analysis Pinch Point Analysis is used to Pinch Point Analysis and 03-Jan-12 28-Aug-12 Currently being evaluate scenarios where a single fire Suggested Procedure 0rentlybei may damage all the credited paths for eDeveloped a Key Safety Function (KSF).
Develop Fire Probabilistic Risk Assessment (PRA)
Fire Risk Quantification 1 with most conservative assumptions on cable Complete (F&O routing, fire modeling and circulate Fire PRA Peer Review 23-Jan-12 27-Jan-12 resolution in progress) likelihood were used. Many F&Os were due to the status of incompletion or lack of refinement for high-risk scenarios.
Use of 9 8 th percentile Heat release 1
Reactor Building rate (HRRs) for transients and lack of Scoping Fire Modeling 08-Nov-12 01-May-12 walkdown completed crediting manual suppression before fire damages targets were main causes of conservatism in the model.
Crediting the delay of Flamemastic coatings for fire propagation to May be extended to address follow-up Self Igniting Cable Fire Scenarios 07-Feb-12 24-Apr-12 adjacent cable trays F&O resolution for top risk-contributing fire areas in progress E-2
Enclosure Status and Schedule of Major NFPA 805 Milestones (as of March 14, 2012) mevision i wa5 resirlcwe uo llmiieu Circuit Failure Mode and components. Revision 2 will cover 29-Aug-i 1 31-May-12 Revision 2 in Progress Likelihood Analysis more components including those with hiah risk.
Findings &
Development of Main Control 07-Feb-12 07-May-12 Observations (F&Os)
Room Analysis resolution of peer review in progress In progress for top May be extended to address follow-up Detailed Fire Modeling 07-Feb-12 22-Jun-12 risk-contributing fire F&O resolution areas Scoping approach used; scenarios Includes follow-up F&O resolution and Post-Fire Human Reliability 12-Oct-10 11-Jul-1 2 based in progress for may be extended to address F&O Analysis top risk-contributing resolution fire areas NSCA equipment to equipment logic being incorporated; first Quantification 2 includes model Fire Risk Quantification 2 23-Jan-12 24-Jun-12 cutset review planned refinement for high-risk scenarios and in April; initial peer review F&O resolution.
Quantification 2 in progress.
Review focus is on the following Initial Peer review elements: Fire Scenario Selection, Follow-Up Focused Fire PRA Peer 25-Jun-12 29-Jun-12 F&Os being Human Reliability Analysis, Review addressed Quantification, and Uncertainty Analysis Some F&Os will not be resolved until F&O Resolution of Initial and after SER is approved (e.g., fire F&olRsolution or Iial a6-Feb-12 6-Nov-12 In-Progress procedures based on the fire PRA Follow-up Peer Reviews and fire risk evaluations need prior NRC approval)
E-3
Enclosure Status and Schedule of Major NFPA 805 Milestones (as of March 14, 2012) r eL, quipirwi Lu equipment logic being incorporated; first Those F&Os affecting the PRA model cutset review planned and resolvable before LAR approval in April; will be resolved prior to Quantification Fire Risk Quantification 3 12-Jan- 12 13-Sep-12 Quantification 2 in 3, which represents the PRA model progress.
for final risk evaluation and LAR Quantification 3 will be submittal.
continuing to address follow-up peer review F&O resolutions.
Methodology of all This is completion of the PRA model Revise and Complete the PRA elements for FRE and LAR submittal; final PRA Probabilistic Risk Assessment 12-Jan-12 6-Nov-12 completed; documentation will be completed by documentation of final November 6, 2012 for PORC/NSRB PRA will be started after quantification 3.
FREs will be performed using a Fire Risk Evaluations (FREs) 27-Mar-12 25-Jul-I 2 Pilot FRE process staggered approach for each fire area started on March 6 based on PRA quantification and fire area assessments In order to facilitate timely review, the NFPA 805 LAR will be prepared and Prep of LAR and Transition Report reviewed by BFN PORC and TVA NSRB in 3 Groups.
(Executive Summary, Sections: 1, 2, Prepare Group I Segment of [AR 23-Jul-12 27-Jul-12 3, 4.2.2, 4.2.3, 4.4, 4.6 & 4.7 -
submittal__Attachments: E, K, M, N, 0 & P)
BFN Group 1ITechnical Review 27-Jul-12 03-Aug-12 BFN Group 1 Licensing Review 30-Jul-12 06-Aug-12 BFN Group 1 PORC Subcommittee Review 08-Aug-1 2 17-Aug-1 2 E-4
Enclosure Status and Schedule of Major NFPA 805 Milestones (as of March 14, 2012) t/-%Lru[yFI UI51, OUI*AWIRSI. z'+. 1I.0, Prepare Group 2 Segment of LAR 27-Sep-12 01-Oct-12 4.2.1.1, 4.2.1.2, & 4.3 - Attachments:
submittal B, D, H, I, L & T)
BFN Group 2 Technical Review 01-Oct-12 05-Oct-12 BFN Group 2 Licensing Review 02-Oct-12 09-Oct-12 BFN Group 2 PORC Subcommittee Review 15-Oct-12 19-Oct-1 2 (Acronym List, Sections: 4.2.1.3, Prepare Group 3 Segment of LAR 22-Oct-12 26-Oct-12 4.2.1.4, 4.2.4, 4.8, 5 & 6-Attachments:
submittal__C,F,G,J,Q,R,S,U,V,W)
BFN Group 3 Technical Review 26-Oct-12 02-Nov-12 BFN Group 3 Licensing Review 29-Oct-12 05-Nov-12 BFN Group 3 PORC Subcommittee Review 05-Nov-12 12-Nov-1 2 Final PORC/NSRB Approval 12-Nov-12 05-Dec-12 Submit LAR to NRC 06-Dec-12 17-Dec-12 Final approvals and executive Submit____________________
to_ _____ _ _signature process E-5