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Category:Letter
MONTHYEARIR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual 2024-09-03
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator2024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup 05000260/LER-2024-001-01, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-04-17017 April 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000259/LER-2024-001, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-04-11011 April 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure 05000260/LER-2024-001, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-02-16016 February 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure 05000259/LER-2023-003, Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage2024-01-29029 January 2024 Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage 05000259/LER-2022-002-01, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator2023-10-12012 October 2023 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator 05000260/LER-2023-001-01, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure2023-09-18018 September 2023 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line Due to Fatigue Failure 05000260/LER-2023-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2023-08-0404 August 2023 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2022-003-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure2023-07-31031 July 2023 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure 05000259/LER-2023-002, Full Reactor Scram Due to an Oscillation Power Range Monitor (OPRM) Confirmation Density Algorithm (CDA) Trip2023-07-17017 July 2023 Full Reactor Scram Due to an Oscillation Power Range Monitor (OPRM) Confirmation Density Algorithm (CDA) Trip 05000259/LER-2023-001-01, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm2023-06-13013 June 2023 High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm 05000260/LER-2023-001, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line2023-04-19019 April 2023 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line 05000259/LER-2023-001, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm2023-03-27027 March 2023 High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm 05000259/LER-1922-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2023-02-0606 February 2023 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2022-003, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2023-01-31031 January 2023 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line 05000296/LER-2022-002, Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate2022-12-19019 December 2022 Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate 05000259/LER-2022-002, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator2022-09-12012 September 2022 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator 05000296/LER-2022-001, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2022-07-11011 July 2022 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2021-001-01, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay2022-07-0606 July 2022 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay 05000259/LER-2022-001, From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line2022-03-16016 March 2022 From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line 05000259/LER-2021-001, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay2021-11-22022 November 2021 Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay ML20160A0232020-06-0404 June 2020 SR 2020-001-00 for Browns Ferry Nuclear Plant (Bfn),Inoperable Oscillating Power Range Monitor (OPRM) Instrumentation 05000296/LER-2017-0022017-12-29029 December 2017 4kV Shutdown Board Potential Transformer Primary Fuses Do Not Coordinate with Secondary Fuses, LER 17-002-00 for Browns Ferry Nuclear Plant, Unit 3 Regarding 4kV Shutdown Board Potential Transformer Primary Fuses Do Not Coordinate with Secondary Fuses 05000296/LER-2017-0012017-10-31031 October 2017 Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications, LER 17-001-00 for Browns Ferry Nuclear Plant, Unit 3, Regarding Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications 05000260/LER-2017-0042017-07-0707 July 2017 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints, LER 17-004-00 for Browns Ferry, Unit 2, Regarding Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000260/LER-2017-0032017-05-30030 May 2017 Manual Reactor Scram Initiated During Startup Due to Multiple Rods Inserting, LER 17-003-00 for Browns Ferry Nuclear Plant, Unit 2 Regarding Manual Reactor Scram Initiated During Startup Due to Multiple Rods Inserting 05000259/LER-2017-0022017-04-27027 April 2017 Unauthorized Firearm Introduced into the Protected Area, LER 17-002-00 for Browns Ferry, Unit 1, Regarding Unauthorized Firearm Introduced into the Protected Area 05000260/LER-2017-0022017-04-24024 April 2017 Inoperable Primary Containment Isolation Valve Resulting in Condition Prohibited by Technical Specifications, LER 17-002-00 for Browns Ferry, Unit 2, Regarding Inoperable Primary Containment Isolation Valve Resulting in Condition Prohibited by Technical Specifications 05000260/LER-2017-0012017-04-14014 April 2017 High Pressure Coolant Injection Safety System Functional Failure Due to a Blown Fuse, LER 17-001-00 for Browns Ferry, Unit 2, Regarding High Pressure Coolant Injection Safety System Functional Failure Due to a Blown Fuse 05000259/LER-2016-0022016-09-19019 September 2016 High Pressure Coolant Injection Safety System Functional Failure due to Inoperability of Primary Containment Isolation Valve, LER 16-002-00 for Browns Ferry, Unit 1, Regarding High Pressure Coolant Injection Safety System Functional Failure Due to Inoperability of Primary Containment Isolation Valve 05000260/LER-2016-0022016-09-13013 September 2016 High Pressure Coolant Injection System Failure Due To Stuck Contactor, LER 16-002-00 for Browns Ferry Nuclear Plant, Unit 2, Regarding High Pressure Coolant Injection System Failure Due To Stuck Contactor 05000260/LER-2016-0012016-08-16016 August 2016 High Pressure Coolant Injection Safety System Functional Failure due to a Blown Fuse and a Failed Relay, LER 16-001-00 for Browns Ferry, Unit 2, Regarding High Pressure Coolant Injection Safety System Functional Failure Due to a Blown Fuse and a Failed Relay 05000296/LER-2016-0062016-08-0505 August 2016 1 OF 8, LER 16-006-00 for Browns Ferry Nuclear Plant, Unit 3, Regarding High Pressure Coolant Injection System Found to be Inoperable During Testing 05000259/LER-2016-0012016-06-21021 June 2016 Failure of 4kV Shutdown Board Normal Feeder Breaker Results in Actuations of Emergency Diesel Generators and Containment Isolation Valves, LER 16-001-00 for Browns Ferry, Unit 1, Regarding Failure of 4kV Shutdown Board Normal Feeder Breaker Results in Actuations of Emergency Diesel Generators and Containment Isolation Valves 05000296/LER-2016-0052016-06-17017 June 2016 Automatic Depressurization System Valve Inoperability Exceeded Technical Specification Limits, LER 16-005-00 for Browns Ferry, Unit 3, Regarding Automatic Depressurization System Valve Inoperability Exceeded Technical Specification Limits 05000296/LER-2016-0042016-06-0606 June 2016 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints, LER 16-004-00 for Browns Ferry, Unit 3, Regarding Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000296/LER-2016-0032016-04-25025 April 2016 Main Steam Isolation Valve Leaking in Excess of Technical Specification Requirements, LER 16-003-00 for Browns Ferry Nuclear Plant Unit 3 Regarding Main Steam Isolation Valve Leaking in Excess of Technical Specification Requirements 05000296/LER-2016-0022016-04-22022 April 2016 Improperly Installed Switch Results in Condition Prohibited by Technical Specifications, LER 16-002-00 for Browns Ferry Nuclear Plant, Unit 3, Regarding Improperly Installed Switch Results in Condition Prohibited by Technical Specifications 05000296/LER-2016-0012016-03-21021 March 2016 Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications and Safety System Functional Failure, LER 16-001-00 for Browns Ferry, Unit 3, Regarding Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications and Safety System Functional Failure 05000260/LER-2015-0022016-03-17017 March 2016 High Pressure Coolant Injection System Inoperable due to Manual Isolation of Steam Leak I, LER 15-002-01 for Browns Ferry, Unit 2, Regarding High Pressure Coolant Injection System Inoperable Due to Manual Isolation of Steam Leak ML1108400352011-03-22022 March 2011 Letter Re Licensee Event Report Which Occurred on December 22, 2010, Concerning Low Pressure Coolant Injection Operability, TVA Expects to Submit a Revised LER by April 15, 2011 ML1015505752010-04-0707 April 2010 Event Notification for Browns Ferry on Spill of Water Containing Tritium ML1015505632008-01-10010 January 2008 Event Notification for Browns Ferry on Offsite Notification - Spill of Water Containing Tritium 2024-07-08
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[I!fil Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 4, 2020 10 CFR 50.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296
Subject:
Browns Ferry Nuclear Plant (BFN) - Special Report 296/2020-001 for Inoperable Oscillating Power Range Monitor (OPRM) Instrumentation In accordance with Technical Specification (TS) 5.6.7, OPRM Report, this letter provides notification of inoperable OPRM instrumentation. Due to the inoperability of BFN Unit 3 OPRM instrumentation channels during the implementation of the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) License Amendment, TS 3.3.1.1, Reactor Protection System (RPS)
Instrumentation, Condition I was entered and associated Required Action I.3 of TS 3.3.1.1 was taken to immediately initiate action to submit an OPRM report in accordance with TS 5.6.7.
BACKGROUND INFORMATION:
On March 10, 2020, the MELLLA+ License Amendment was implemented for BFN Unit 3. At that time BFN Unit 3 was in Mode 5, Refueling. One of the changes approved by the NRC in the MELLLA+ License Amendment was the use of the Detect and Suppress Solution -
Confirmation Density (DSS-CD) thermal-hydraulic stability solution, instead of the previous approved Option III thermal-hydraulic stability solution. At the time of implementation, the BFN Unit 3 OPRMs were configured for compliance with DSS-CD thermal-hydraulic stability solution. However, completion of certain MELLLA+ testing and placing the confirmation density algorithm of the DSS-CD in service are required for the OPRMs to be considered Operable.
These activities were not planned to be completed until after the OPRM Condition of Applicability (i.e., > 18% Rated Thermal Power (RTP)) was reached following startup from the BFN Unit 3 Spring 2020 refueling outage. As a result, all channels of the OPRM Upscale Function were inoperable on March 26, 2020, when BFN Unit 3 reached 18% RTP following startup from the refueling outage. The applicable Required Actions of TS 3.3.1.1 were taken prior to BFN Unit 3 reaching 18% RTP. Subsequently, on April 1, 2020, power on BFN Unit 3 was reduced below 18% RTP in preparation for a forced outage. On April 6, 2020, during
U.S. Nuclear Regulatory Commission Page 2 June 4, 2020 startup from the forced outage, the OPRM Condition of Applicability was again reached. At that time, all applicable Required Actions of TS 3.3.1.1 for inoperable OPRM channels were satisfied.
TS Table 3.3.1.1-1, Function 2.f, requires three of the four OPRM Upscale channels to be Operable. With one or more required OPRM Upscale channels inoperable, TS 3.3.1.1 Required Action A.1 requires the inoperable channels to be placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. With all four of the OPRM Upscale channels inoperable, the associated RPS trip capability is not maintained and TS 3.3.1.1 Required Action C.1 requires restoration of RPS trip capability to be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If a Required Action and associated Completion Time is not met, TS 3.3.1.1 Required Action D.1 requires entry into the Condition referenced in Table 3.3.1.1-1 for the channel. For channels associated with Function 2.f, Table 3.3.1.1-1 references Condition I.
TS 3.3.1.1 Condition I includes Required Actions to immediately initiate action to implement Manual Backup Stability Protection Regions (Required Action I.1), within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> implement the Automated Backup Stability Protection Scram Region (Required Action I.2), and immediately initate action to submit an OPRM report in accordance with TS 5.6.7 (Required Action I.3).
Action was initiated, on March 10, 2020, to submit the OPRM report in accordance with TS 5.6.7. TS 5.6.7 requires, when an OPRM report is required by Condition I of TS 3.3.1.1, that the report be submitted to NRC within the following 90 days. The OPRM report is required to outline the preplanned means to provide backup stability protection, the cause of the inoperability and the plans and schedule for restoring the required instrumentation channels to Operable status.
CAUSE OF THE INOPERABILITY:
The cause of the inoperability of the OPRM Upscale channels was a preplanned evolution to implement the BFN Unit 3 MELLLA+ License Amendment with the unit in Mode 1 above 18% RTP (i.e., the condition of Applicability for the OPRM Upscale channels) following startup from the BFN Unit 3 Spring 2020 refueling outage. On March 10, 2020, when the BFN Unit 3 MELLLA+ License Amendment was implemented, the OPRM Upscale channels were configured for compliance with the DSS-CD thermal-hydraulic stability solution. However, certain MELLLA+ testing had not been completed and the confirmation density algorithm of the DSS-CD had not been placed in service. These activities were required to be completed for the OPRM Upscale channels to be considered Operable. Therefore, upon implementing the BFN Unit 3 MELLLA+ License Amendment and when BFN Unit 3 first reached 18% RTP, the OPRM Upscale channels were inoperable.
PREPLANNED MEANS OF BACKUP STABILITY PROTECTION:
Upon declaring the OPRM Upscale channels inoperable and prior to entering the OPRM Condition of Applicability, the following preplanned means of backup stability protection were implemented.
x Operations personnel immediately initiated action to implement the Manual Backup Stability Protection Regions in accordance with TS 3.3.1.1 Required Action I.1. Operations personnel were required to immediately verify unit operation was outside of Manual Backup
U.S. Nuclear Regulatory Commission Page 3 June 4, 2020 Stability Protection Regions, i.e., Region 1 (Scram) and Region 2 (Controlled Entry) of the power/flow map. In addition, Operations personnel were required by procedures to monitor for thermal-hydraulic oscillations if unit operation was within 10% of the rated core flow or power of Region 2 of the power/flow map. Operations personnel were also required by procedures to re-perform the verifications each time core flow was lowered by 10% or reactor power was raised by 5%, when flow was below 75% of rated core flow and power was above 18% rated thermal power.
x In accordance with TS 3.3.1.1 Required Action I.2, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the Automated Backup Stability Protection Scram Region was implemented. To implement the Automated Backup Stability Protection Scram Region, Maintenance personnel implemented the modified Average Power Range Monitor (APRM) Flow Biased Simulated Thermal Power - High Scram setpoints specified in the Core Operating Limits Report for the Automated Backup Stability Protection Scram Region.
PLANS AND SCHEDULE FOR RESTORING THE REQUIRED INSTRUMENTATION CHANNNELS:
On April 24, 2020, upon completion of certain MELLLA+ testing and placing the confirmation density algorithm of the DSS-CD in service, the OPRM Upscale channels were declared Operable.
There are no new regulatory commitments associated with this submittal. If there are any questions or if additional information is needed, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully, S. M S M. Bono o Site Vice President cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant