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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, Post Office Box 2000, Decatur, Alabama 35609-2000 February 28, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No. 50-259 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN)-- UNIT 1 - REGULATORY FRAMEWORK FOR THE RESTART OF UNIT 1
Reference:
TVA letter dated December 13, 2002, Regulatory Framework for the Restart of Unit 1.
Table 1 of the referenced letter listed NRC generic communications for which TVA has outstanding actions. In the generation of that table, TVA inadvertently omitted Bulletin 79-12, Short Period Scrams At BWR Facilities. This discrepancy was discovered during a review of outstanding commitments on Unit 1. Actions for Bulletin 79-12 have been completed on Units 2 and 3, and TVA's commitment management program still contains the commitment to implement those actions on Unit 1. The commitment was appropriately included in the Unit 1 restart scope. TVA has reviewed Table 1 in the December 13, 2002, letter, and no other omissions were identified. TVA has also reviewed all NRC generic letters and bulletins issued since the original Unit 1 framework letter was issued on July 10, 1991. No additional NRC generic letters or bulletins were identified for which TVA has open commitments.
Enclosed is a revision to Table 1 of the referenced letter which includes Bulletin 79-12 as a generic communication action requiring implementation. TVA regrets any confusion this oversight may have caused.
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U.S. Nuclear Regulatory Commission Page 2 February 28, 2003 If you have questions regarding this issue, please call me at (729) 256-2636.
Si cerel T. E. Abney Manager of Li nsin and Industr Affai s Enclosure cc (Enclosur ATTN: Do ent Control Desk Mail Stop OWFN, Pl-35 Washington, D.C. 20555-0001 (Via NRC Electronic Distribution)
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE Table 1: Regulatory Issues Open Commitments to Implement Actions Bulletins:
79-02 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts 79-12 Short Period Scrams At BWR Facilities 79-14 Seismic Analysis for As-Built Safety Related Piping Systems 80-06 Engineered Safety Feature Reset Controls 84-02 Failure of GE Type HFA Relays in Use in Class 1E Safety Systems 86-02 Static "0" Ring Differential Pressure Switches 88-07 Power Oscillation in Boiling Water Reactors 88-10 Nonconforming Molded-Case Circuit Breakers 93-03 Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs 96-03 Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors Generic Letters:
82-33 Instrumentation to Follow the Course of an Accident - R.G. 1.97 83-08 Modification of Vacuum Breakers on Mark 1 Containments 83-28 Salem ATWS 88-11 Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations 88-14 Instrument Air Supply System Problems Affecting Safety Related Equipment 89-06 Safety Parameter Display System 89-08 Erosion/Corrosion-Induced Pipe Wall Thinning 89-10 Safety-Related Motor-Operated Valve Testing and Surveillance 89-16 Installation of a Hardened Wetwell Vent 96-01 Testing of Safety-Related Logic Circuits 96-05 Periodic Verification of Design Basis Capability of Motor Operated Valves 98-01 Readiness of Computer Systems at Nuclear Power Plants NUREG-0737 (TMI Action Plan) Action Items I.D.1 Control Room Design Review I.D.2 Safety Parameter Display Console II.B.3 Post-Accident Sampling System II.E.4.2.1 -4 Containment Isolation Dependability - Implement Diverse Isolation II.F.1.2.C Accident - Monitoring - Containment High Range Radiation II.F.1.2.D Accident - Monitoring - Containment Pressure II.F.I.2.E Accident - Monitoring - Containment Water Level II.F.2.4 (Generic Letter 84-23) - Instrumentation for Detection of Inadequate Core Cooling II.K.3.13 HPCI/RCIC Initiation Levels II.K.3.18 ADS Actuation Modifications II.K.3.28 Qualification of ADS Accumulators
Commitment to Provide Submittal Bulletins:
90-01 Loss of Fill Oil in Rosemount Transmitters 93-02 Debris Plugging of Emergency Core Cooling Suction Strainers Generic Letters:
87-02 Verification of Seismic Adequacy of Mechanical and Electrical Equipment In Operating Reactors 88-20, S 4 Individual Plant Examination of External Events for Severe Accident Vulnerabilities 92-04 Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs 95-07 Pressure Locking and Thermal Binding of Safety-Related and Power Operated Gate Valves 96-06 Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions 97-04 Assurance of Sufficient Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps 98-04 Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss of Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment Requirement for Submittal Within a Specified Period After Actions are Complete Bulletins:
88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE 88-04 Potential Safety Related Pump Loss 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool Cooling Mode Generic Letters:
88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping 89-13 Service Water System Problems Affecting Safety Related Equipment 92-01 Reactor Vessel Structural Integrity 94-02 Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs 94-03 Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs