Letter Sequence Request |
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EPID:L-2022-LLR-0008, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(b) and the Use of Case N-526 (Open) |
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MONTHYEARML21202A2422021-07-21021 July 2021 American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclea Project stage: Request CNL-21-081, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(b) and the Use of Case N-5262022-01-14014 January 2022 Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(b) and the Use of Case N-526 Project stage: Request ML22032A0322022-01-27027 January 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 2, Alternative Request BFN-21-ISI-02 Project stage: Acceptance Review ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) Project stage: RAI 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,. Project stage: Response to RAI 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 Project stage: Request ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 Project stage: Other ML22329A0762022-12-0101 December 2022 Correction of Error in Authorization of Alternative Request BFN-21-ISI-02 Project stage: Other 2022-11-14
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LER-2022-002, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator |
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10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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text
Post Office Box 2000, Decatur, Alabama 35609-2000 September 12, 2022 10 CFR 50.73 10 CFR 50.4(a)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
Licensee Event Report 50-259/2022-002 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator The enclosed Licensee Event Report provides the details of the inoperability of the Browns Ferry Nuclear Plant, Unit 1, High Pressure Coolant Injection System due to a corroded actuator.
The Tennessee Valley Authority is submitting this report in accordance with Title 10 of the Code of Federal Regulations 50.73(a)(2)(v)(D), as any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
There will be a supplement to this Licensee Event Report to provide additional time to complete the root cause evaluation.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Chris L. Vaughn, Site Licensing Manager, at (256) 729-2636.
Respectfully, Manu Sivaraman Site Vice President Enclosure: Licensee Event Report 50-259/2022-002 High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator
U.S. Nuclear Regulatory Commission Page 2 September 12, 2022
cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant
Abstract
On July 12, 2022, during a routine surveillance test, the Browns Ferry Nuclear Plant (BFN), Unit 1, high pressure coolant injection (HPCI) turbine control (governor) valve did not open as expected. Upon investigation, it was discovered that the electro-governor remote hydraulic actuator (EGR) had internal corrosion, which resulted in binding of the pilot plunger and associated pilot bushing and a subsequent failure to supply a hydraulic open signal to the governor valve.
The resulting inoperability of the single-train HPCI system would have prevented HPCI from fulfilling its safety function to mitigate the consequences of an accident.
The causal analysis and corrective actions will be reported later in a supplement to this LER.
Page 6 of 6 VI.
Corrective Actions
Corrective Actions are being managed by the TVAs corrective action program under Condition Report (CR) 1789217.
A. Immediate Corrective Actions
The EGR and remote servo were promptly replaced.
B. Corrective Actions to Prevent Recurrence or to reduce the probability of similar events occurring in the future The corrective actions will be reported later in a supplement to this LER.
VII. Previous Similar Events at the Same Site
A search of LERs from BFN, Units 1, 2, and 3 over the last five years identified no similar events.
VIII. Additional Information
There is no additional information.
IX.
Commitments
There are no new commitments.
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| 05000296/LER-2022-001, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000259/LER-2022-001-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line | Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 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 Line | From Browns Ferry Nuclear Plant, Unit 1 Regarding Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000259/LER-2022-002-01, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator | High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000296/LER-2022-002, Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate | Both Standby Liquid Control Subsystems Inoperable Due to an Insufficient Boron Injection Rate | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000259/LER-2022-002, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator | High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000296/LER-2022-003-01, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure | Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line Due to Fatigue Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000296/LER-2022-003, Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line | Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000259/LER-2022-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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