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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 type:CNL
MONTHYEARCNL-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 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 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 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 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 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. 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CNL-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 CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. 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CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322022-08-22022 August 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-076, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel2022-07-28028 July 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-01-17
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-118 July 2, 2014 Mr. Victor M. Me Cree Regional Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue , NE , Suite 1200 Atlanta , Georgia 30303-1257 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
Confirmatory Action Letter Tier 2 Commitments Related to the Browns Ferry Integrated Improvement Plan
References:
- 1. Letter from TVA to NRC, "Commitments Related to the Browns Ferry Integrated Improvement Plan ," dated August 9, 2013
- 2. Letter from NRC to TVA, "Confirmatory Action Letter- Browns Ferry Nuclear Plant, Units 1, 2, And 3, Commitments Related To The Integrated Improvement Plan ," dated August 22, 2013 [EA 13-185]
- 3. Letter from NRC to TVA, "Browns Ferry Nuclear Plant- Confirmatory Action Letter and Severity Level Ill 10 CFR 50.9 Violation Follow-Up Inspection Report 05000259/2013014, 05000260/2013014, and 05000296/2013014," dated January 27 , 2014 [EA 11-018, EA 11-252, and EA 13-185]
In Reference 1, the Tennessee Valley Authority (TVA) submitted to the Nuclear Regulatory Commission (NRC) commitments associated with continuing efforts to improve performance at the Browns Ferry Nuclear Plant (BFN) . Those commitments were specific to certain actions in the BFN Integrated Improvement Plan (liP) and consisted of Tier 1 (short-term) and Tier 2 (long-term) actions.
Reference 2 documented the NRC review of these commitments, confirmed them as Confirmatory Action letter (CAL) commitment items, and outlined specific requirements for NRC follow-up inspections to assess adequate implementation of Tier 1 and Tier 2 commitment items.
Reference 3 documented the NRC review of TVA's commitments, including the schedule for completion of items and planned key activities, and determined that TVA's actions, when implemented, would provide NRC with the necessary assessment bases to evaluate transition of BFN Unit 1 out of Column 4 of the Agency Action Matrix. Reference 3 also documented the NRC supplemental inspection and closure of the CAL Tier 1 commitment items.
U.S. Nuclear Regulatory Commission Page 2 July 2, 2014 The purpose of this letter is to inform the NRC that the TVA has completed 12 of the 21 actions addressed on the CAL Tier 2 list of commitments provided in Reference 1. In accordance with the requirements of Reference 2, this correspondence also includes the bases for closure of commitment items in the context of the internal TVA reviews established in the liP.
The following list of Tier 2 commitment items have been completed and closure details are provided in the Enclosure to this letter.
Commitment No. 11 - Safety System Reliability Plan (SSRP)
Commitment No. 12- Technical Rigor (TR)
Commitment No. 13 - Continuous Learning Environment (CLE)
Commitment No. 14- Safety Conscious Work Environment (SCWE)
Commitment No. 15- Employee Concerns Program (ECP)
Commitment No. 16 - Design and Configuration Control (DCC)
Commitment No. 17 - Corrective Action Program (CAP)
Commitment No. 18- Governance & Oversight (GOES)
Commitment No. 19 - Inappropriate Reliance on Process (IRP)
Commitment No. 22 - Procedure Use & Adherence (PUA)
Commitment No. 24- Independent Oversight (10)
Commitment No. 29 - Training The closures of the remaining Tier 2 commitment items are expected prior to their commitment dates, and additional correspondence will address them. With regard to the closeout of Fundamental Problems (FPs) , TVA committed to assess the effectiveness of the liP actions and close the FPs in accordance with Procedure 95003-007, "Project Review Boards." This procedure required all closed actions for each FP to be reviewed by BFN's Closure Review Board. These closed actions were also reviewed collectively by BFN's Corrective Action Review Board, which replaced the Effectiveness Review Challenge Board described in Reference 1.
There are no new regulatory commitments made in this letter. Should you have any questions concerning this submittal , please contact Jamie L. Paul, Nuclear Site Licensing Manager at (256)729-2636.
Enclosure:
List of CAL Tier 2 Regulatory Commitments and Bases for Closures cc (Enclosure):
NRC Senior Resident Inspector- Browns Ferry Nuclear Plant
ENCLOSURE Tennessee Valley Authority Browns Ferry Nuclear Plant, Unit 1 List of CAL Tier 2 Regulatory Commitments and Bases for Closures
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date Tier 2 Commitments 11 755599-011 Complete the Safety System Reliability Plan (SSRP) project scope as defined in Problem 05/30/2014 Evaluation Report (PER) Action 760220-003. The SSRP original scope and purpose are defined in PER Action 760220-001 .
Basis for Closure: Maximo Regulatory Commitment No. 114956954 Closure Package 11 - SSRP Summary of Actions :
Completed the SSRP project scope (actions) coded to the 2014 Browns Ferry Nuclear Plant (BFN)
Unit 3 Refueling Outage. The scope of work defined in action 760220-003 included six work orders. Five of the six work orders have been completed . The sixth work order was cancelled based on Engineering determination that no work was required .
12 755599-012 05/31/2014 Close the "Technical Rigor" fundamental problem in accordance with Procedure 95003-007, "Project Review Boards. "
Basis for Closure: Maximo Regulatory Commitment No. 114956949 Closure Package 12- TR Summa[Y of liP Action Plan- Corrective Actions:
Changed Engineering and Operations procedures to address timeliness, rigor, regulatory margin and documentation of Operability Determinations Trained Operations Licensed Operators regarding Operability Determinations (ODs) and examples of ODs that exceeded expectations and incorporated training into Initial License Training gap training and Licensed Operator Requalification training Developed a Training Dispatch to highlight areas from previous errors in ODs Revised the Human Performance (HU) procedure to incorporate the 5 Institute of Nuclear Power Operations (INPO) Technical Conscience Principles from INPO 10-005 document, Principles for Maintaining an Effective Technical Conscience Provided Technical Conscious, HU , and Design Input training E-1 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date Developed/implemented a Plant Operations Review Committee decision-making checklist Included a Subject Matter Expert as part of the engineering Quality Review Team Developed/implemented a change management plan for the revision to the HU procedure to include required training for Operations, Maintenance, Work Control , Chemistry, Radiation Protection, Training, Modifications and Projects, and Safety and Licensing personnel Revised Engineering Leadership Expectations to include the expectation to use the appropriate HU Tools for Managers and Supervisors during pre-job briefs Established an Operability Determination Review Board 13 755599-013 Close the "Continuous Learning Environment" fundamental problem in accordance with 05/31/2014 Procedure 95003-007, "Project Review Boards. "
Basis for Closure: Maximo Regulatory Commitment No. 114956943 Closure Package 13- CLE Summary of liP Action Plan- Corrective Actions :
Established accountabilities within the Performance Review and Development process for Department Directors and Managers Filled position/assigned personnel for a departmental specified position to manage Performance Improvement, to include Self Assessment, Benchmarking and Operating Experience (OE)
Performed/presented/developed/implemented training for Continuous Learning Environment using a Training Needs Analysis Benchmarked the nuclear industry and reviewed INPO guidance specified in INPO 09-011 ,
Achieving Excellence in Performance Improvement Utilized the results of the procedural reviews and benchmarking and revised Self Assessment and Benchmarking Performance Indicators Verified completion of the coordination with the corporate Corrective Action Program (CAP) group and addressed the weaknesses in trending Verified completion of the development of Trending High Impact Team (HIT) charter and implemented HIT meetings to improve trending process" I
E-2 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date 14 755599-014 Close the "Safety Conscious Work Environment" fundamental problem in accordance with 05/31/2014 Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956937 Closure Package 14- SCWE Summarv of liP Action Plan- Corrective Actions:
Verified that actions to acknowledge receipt of the 2011 final SYNERGY Independent Safety Culture report & results" were completed by applicable BFN departments Revised the Third Party Independent Nuclear Safety Culture Assessment procedure and other applicable procedures to address trending of SCWE issues 15 755599-015 Close the "Employee Concerns Program" fundamental problem in accordance with 05/31/2014 Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956929 Closure Package 15 - ECP Summaey of liP Action Plan - Corrective Actions:
Developed/implemented a standards and expectations document for the fleet ECP program that included direction for ECP specialists to follow for day-to-day activities Benchmarked industry best plants for ECP procedures and best practices to determine gaps to excellence in the TVA ECP program . Included in the benchmarking activity assessing possible improvements in qualification and training requirements for Fleet ECP Specialists. Revised ECP procedures to industry standards, as necessary, and implemented industry best practices, as applicable Provided an experienced ECP specialist to review status of the ECP and identify gaps to excellence and expectations 16 755599-016 Close the "Design and Configuration Control" fundamental problem in accordance with 06/30/2014 Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956917 Closure Package 16 - TR Summary of II P Action Plan - Corrective Actions: I E-3 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date BFN Director of Engineering performed a formal brief to all BFN engineering managers identifying the expectation that the Design Change Notice (DCN) design review process, in accordance with the procedures, is detailed and rigorous Benchmarked/incorporated Design Change process metrics into Design Review Meetings, Design Review Boards, and Quality Review Teams that promote building quality into design products Verified the completion of action to implement a leadership assessment process to rigorously evaluate supervisor and management alignment to the nuclear fleet fundamentals Verified completion of actions including procedure revisions to clarify roles and responsibilities for engineering reviews, updates on qualifications of Oversight Task Engineers Performed performance observations (ePOP) to capture lessons learned from Design Review Meetings, Design Review Boards, and Quality Review Teams focusing on procedural requirements and design adequacy 17 755599-017 Close the "Corrective Action Program" fundamental problem in accordance with 06/30/2014 Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956914 Closure Package 17 - CAP Summarv of liP Action Plan - Corrective Actions:
Established dedicated positions for Cause Analysis Subject Matter Experts at corporate and each TVA nuclear site Established positions for a core group of dedicated cause analysts at each site whose primary '
duty is to perform as the root causes analyst or as a root cause team members Updated Qualification Requirements and Training Program or Training Program Document Performance Indicator based on weaknesses identified in analyses; delivered training Implemented, with external CAP expertise, a CAP model of excellence that defines the organizations roles, responsibilities, and behaviors Revised New Employee Experience and Annual CAP Continuing Training to include the Chief Nuclear Officer message on CAP vision of excellence E-4 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date Benchmarked top-performing utility Problem Evaluation Report Screening Committee (PSC) meetings Required that a PSC Meeting Gatekeeper be appointed at each PSC meeting to ensure that a current copy of the procedure is being used Developed Desktop Guidance for Performance Improvement Coordinators that illustrates steps for Common Cause Analysis (CCA) development Established monthly recognition of "4-star CCAs Developed standard Trending Report to provide departments with capability to obtain trend data Revised NPG Cause Evaluation Manual to include a Common Cause Analysis methodology that can be used to support low level trending Added a Living List of Potential Trends to the Corrective Action Review Board (CARB) agenda to challenge daily for generation of trend PERICCA Developed/implemented standard report to monitor application of cause codes for A and B-level PERs Completed a Training Needs/Job Task Analysis to include a skills/experience development process Developed/issued a Causal Analysis Manual to supplement the requirements of Root Cause Analysis (RCA) and Apparent Cause Evaluation procedures Developed/implemented training program for Department CARB/CARB/PICs/RCA responsible managers/RCA team members 18 755599-018 Close the "Governance & Oversight" fundamental problem in accordance with 06/30/2014 Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956900 Closure Package 18 - GOES Summary of liP Action Plan - Corrective Actions:
Developed seminar package and delivered at BFN, Sequoyah Nuclear Plant (SQN), Watts Bar Nuclear Plant (WBN), and TVA Corporate to ensure consistency in content and message to effectively reinforce the application and interrelations of the Nuclear Operating Model (NOM),
E-5 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date GOES model, and the implementing procedure.
Conducted BFN site leadership (first-line supervisor and above) seminars to reinforce the application of the NOM Conducted corporate seminars with all Corporate Functional Area Managers (CFAMs) and Corporate Functional Managers with support from CFAMs to reinforce the application of the NOM Revised the Leadership Development Training Program Description to include training on the NOM and its application to all NPG leaders (first-line supervisors and above)
Implemented agenda topics to specifically address issues related to site or corporate adherence to the standards and expectations associated with the NOM and GOES model in corporate Monthly Review Meetings and Strategic Council meetings Revised the existing GOES metric to include designated CFAM monthly performance summaries as inputs Established a GOES secondary metric, which can be used as a means to gauge alignment of the BFN organization to understanding the elements of the NOM Conducted a snapshot self-assessment to address effectiveness in implementing the NOM as discussed in upper tier apparent cause 19 755599-019 Close the "Inappropriate Reliance on Process" fundamental problem in accordance with 06/30/2014 Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956896 Closure Package 19- IRP Summary of liP Action Plan- Corrective Actions:
Proposed revision to the peer team for the Clearance Procedure to Safely Control Energy procedure to state the program owner (i.e., Operations Manager) and the owner's roles and responsibilities Proposed revision to the peer team for the Housekeeping procedure to establish a program owner and define the owner's roles and responsibilities Proposed revision to the peer team for Plant Operations Fire Protection procedure to establish a program owner and define the owner's roles and responsibilities E-6 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date Revised procedure the Foreign Material Control procedure to establish a program owner and define the owner's roles and responsibilities Developed/issued a Nuclear Operating Experience Report for WBN and SON to review the Apparent Cause Evaluation associated with fundamental problem for lessons learned regarding process/program ownership and owner's roles and responsibilities Verified completion of Root Cause corrective action to prevent recurrence from Management and Leadership Standards: Using the NOM as a model, utilized the Excelerated Leadership Strategic Performance Management process to ensure management alignment in the ownership and accountability for leadership expectations at BFN 22 755599-022 08/31/2014 Close the "Procedure Use & Adherence" fundamental problem in accordance with Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956855 Closure Package 22 - PUA Summary of liP Action Plan - Corrective Actions:
Implemented a leadership assessment process to rigorously evaluate supervisor and management alignment to the nuclear fleet fundamentals, and specific to this root cause, NPG leadership fundamental 6, "We Manage to a Common Set of Effective Processes and Structures, which includes a commitment to 'know, understand, and execute standard policies, programs, processes, and procedures"'
Determined the population of newly hired Managers and Supervisors which need enrollment in TVA's Supervisor Academy and enrolled population not currently in process Performed a TVA oral board for each department which reinforces TVA Nuclear Fleet Leadership Fundamentals and TVA policies regarding PUA Conducted an independent review of the quality of Operations and Maintenance Procedures Issued a PUA read and sign document for "Condition of Employment" to all currently employed First Line Supervisors (FLSs)
Ensured that each FLS and Manager included in their Individual Development Plans (lOPs) a reinforcement of PUA Revised the Oversight of the Human Performance Program procedure to include PUA trends in the E-7 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date behavior observation program and to add consistent enforcement of correct PUA Created a HU Fundamentals observation/roll-up metric report to monitor enforcement of PUA Performed a snap shot self assessment of HU issues related to PUA by monitoring the progress of HU gap analysis corrective actions 24 755599-024 Close the "Independent Oversight" fundamental problem in accordance with 08/31/2014 Procedure 95003-007, "Project Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956838 Closure Package 24 - 10 Summarv of liP Action Plan - Corrective Actions:
Revised NPG "Organization and Administration" procedure to require the Vice President (VP) of Oversight, Site VPs, and the Nuclear Safety Review Board (NSRB) Chair to brief the Senior VP (SVP) of Operations and the Chief Nuclear Officer (CNO) on their assessment of the health of the relationship between independent oversight and each site (and corporate) leadership team including the NPG corporate office Developed/Implemented an Independent Oversight Policy Revised Quality Assurance (QA) procedures to provide guidance for how nuclear and regulatory risk will be factored into the decisions of when audits and assessments should be conducted , when schedules are adjusted, and the risk priorities for the activities to be audited and assessed Revised the Fleet Handbook to explicitly describe the importance of independent oversight Revise the fleet metrics to include and prominently display selected indicators from the Oversight Key Performance Indicators Performed a staff assessment to determine if the staffing in QA is adequate Conducted a review of TVA board policies involving regulatory risk Revised the Nuclear Safety Oversight procedure to require the NSRB to identify and escalate issues that are not being effectively analyzed and addressed , as well report periodically to the CNO and SVP Operations 29 755599-029 Close the "Training" fundamental problem in accordance with Procedure 95003-007, "Project 12/15/2014 E-8 of 9
REGULATORY COMMITMENTS Commitment liP PER Commitment Description Commitment No. Action No. Due Date Review Boards."
Basis for Closure: Maximo Regulatory Commitment No. 114956742 Closure Package 29- Training Summarv of liP Action Plan- Corrective Actions:
Revised the Senior Training Council (STC) agenda to provide greater training oversight and to promote member accountability Required mentoring for new Training Advisory Committee (TAC) chairs and required the assignment of a STC member as a mentor for each station TAC Developed/implemented a long range integrated staffing plans for Maintenance, Engineering ,
Radiation Protection, and Chemistry Established a staffing performance indicator that will be monitored by station and corporate management Increased current Engineering Support Personnel instructor level at BFN training to 3 Had engineering assistant director, engineering director, and department training coordinator (DTC) read and sign expectations letter for DTC full time job Performed training needs analyses and established tracking of training needs and requests to improve identification of knowledge and skill deficiencies Required completing formal analysis for top 3 issues identified during Curriculum Review Committee (CRC) meetings Required two supervisors for CRC quorum Required performance analysis to be performed as part of the analysis for root cause and upper tier apparent cause level PERs or document why a performance analysis is not required Implemented Systematic Approach to Training for engineering , reinforcing department ownership and use of training to improve performance E-9 of 9