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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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April 15, 2008 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. 50-296 Tennessee Valley Authority )
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 - BOILING WATER REACTOR VESSEL INTERNALS PROJECT (BWRVIP) - NOTIFICATION OF DEVIATION FROM BWRVIP-41, BWR JET PUMP ASSEMBLY INSPECTION AND FLAW EVALUATION GUIDELINES In accordance with a prior agreement with the NRC, BWR utilities that are part of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) agreed that participating licensees will provide notification to the NRC staff of a decision by the licensee to not fully implement the applicable BWRVIP product. Therefore, TVA is providing notification that BFN Unit 3 will not fully implement the subject guidance of BWRVIP-41, Revision 1, BWR Jet Pump Assembly Inspection And Flaw Evaluation Guidelines.
A deviation disposition was prepared, reviewed, and approved in accordance with BWRVIP-94, Revision 1, BWR Vessel and Internals Project Program Implementation Guide, and TVA internal procedures. The deviation disposition provides assurance that there are no safety implications or reliability concerns with the deviation.
The BFN Unit 3 deviation concerns one item. BFN Unit 3 is not meeting the requirements for an EVT-1 visual examination of the riser brace to yoke welds (Welds RB-2a, b, c, and d) for Jet Pumps 5/6 stipulated by BWRVIP-41, Revision 1.
U.S. Nuclear Regulatory Commission Page 2 April 15, 2008 During the In-Vessel Visual Inspection of Unit 3 performed in 1992 in preparation for restart, crack indications were identified at the two attachment welds of the riser brace to the riser pipe (RS-8 and RS-9) adjacent to Jet Pump Number 5 at reactor vessel 90° azimuth. A repair clamp was installed between the riser brace yoke and the riser pipe to capture the riser brace and perform the function of the deficient weld attachment. The repair clamp was also designed so as to allow future inspections of the existing cracks. However, it was discovered during the initial baseline inspection that the repair clamp obstructed inspection of the riser brace to yoke (RB-2) welds. The RB-2 welds are categorized as a medium priority location. A baseline inspection has been conducted for all three units at BFN, and no indications have been observed at this location. This provides a reasonable level of assurance that the RB-2 welds associated with Jet Pumps 5/6 are intact. Therefore, BFN has waived the EVT-1 examination for the Unit 3 Jet Pumps 5/6 (ONLY) in accordance with BWRVIP-41, Revision 1. The vendor recommended inspection will continue to be performed every other refueling outage to ensure that the jet pump riser pipe indications have not increased in length and the repair clamp is performing its function as designed. This inspection will provide us with information as to whether any signs of increased flow-induced vibration are present, which would be indicative of failure of the RB-2 welds.
The next scheduled inspection to ensure that the jet pump riser pipe indications have not increased in length and the repair clamp is performing its function as designed will be performed during the U3C14 Refueling Outage in 2010. Since this inspection will serve in place of the BWRVIP-41 mandated inspection of the RB-2 welds, this deviation disposition will remain in effect until that time. Following the next inspection, the results will be evaluated and another deviation disposition prepared if results are satisfactory.
Evaluating this condition every four years will provide greater attention to this location than would be obtained otherwise by performing the BWRVIP-41 mandated inspection.
This deviation is effective for the next two BFN Unit 3, two-year fuel cycles (Cycle 13-Spring 2006 to Spring 2008, and Cycle 14-Spring 2008 to Spring 2010) only. This
U.S. Nuclear Regulatory Commission Page 3 April 15, 2008 notification is being transmitted for information only.
TVA is not requesting any specific action from the NRC.
There are no new regulatory commitments in this letter. If you have any questions, please contact me at (256) 729-2636.
Sincerely, Original signed by:
D. T. Langley Manager of Licensing and Industry Affairs cc: See Page 4
U.S. Nuclear Regulatory Commission Page 4 April 15, 2008 cc:(Via NRC Electronic Distribution):
Mr. Jon H. Thompson, BWRVIP Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 09H4) 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Rebecca L. Nease, 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 Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Ms. Eva A. Brown Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Randy Stark EPRI BWRVIP Program Manager P.O. Box 10412 3412 Hillview Avenue Palo Alto, California 94303 Mr. Robert Carter EPRI BWRVIP Assessment Manager EPRI NDE Center P.O. Box 217097 1300 W. T. Harris Boulevard Charlotte, North Carolina 28221
U.S. Nuclear Regulatory Commission Page 5 April 15, 2008 JEE:JWD:BAB cc: G. P. Arent, EQB 1B-WBN W. R. Campbell, LP 3R-C S. M. Douglas, POB 2C-BFN D. C. Matherly, Jr., BFT 2A-BFN R. F. Marks, Jr., PAB 1C-BFN L. E. Nicholson, BR 4X-C R. G. West, NAB 2A-BFN B. A. Wetzel, BR 4X-C S. A. Vance, WT 6A-K E. J. Vigluicci, ET 11A-K NSRB Support, LP 5M-C EDMS-WT CA-K s:\lic\submit\subs\Unit 3 BWRVIP Notification of Deviation 0408.doc