05000348/LER-2023-002, Residual Heat Removal Pump Inoperable for Longer than Allowed by Technical Specifications
| ML23333A215 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/29/2023 |
| From: | Dean E Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LER 2023-002-00 | |
| Download: ML23333A215 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3482023002R00 - NRC Website | |
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A Southern Nuclear November 29, 2023 Docket Nos.: 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Regulatory Affairs Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2023-002-00 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 NL-23-0870 Residual Heat Removal Pump Inoperable for Longer Than Allowed by Technical Specifications Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73{a){2){i){B), Southern Nuclear Operating Company is submitting the enclosed Licensee Event Report for Joseph M. Farley Nuclear Plant, Unit 1. The enclosed LER describes a condition which was prohibited by Technical Specification.
This letter contains no NRC commitments. If you have any questions regarding this submittal, please contact Gene Surber at {334) 661-2265.
Respectfully submitted, Edwin Dean Ill Vice President-Farley Nuclear Plant ED/kmo/cbg Enclosure: Unit 1 Licensee Event Report 2023-002-00 cc:
Regional Administrator - Region II NRR Project Manager - Farley Nuclear Plant Senior Resident Inspector - Farley Nuclear Plant RTYPE: CFA04.054
Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2023-002-00 Residual Heat Removal Pump Inoperable for Longer Than Allowed by Technical Specifications Enclosure Unit 1 Licensee Event Report 2023-002-00
Abstract
At approximately 10:00 CDT on October 2, 2023, with Joseph M. Farley Nuclear Plant (FNP) Unit 1 in Mode 1 and 100 percent power, the 1 B residual heat removal (RHR) pump failed to start on demand during the quarterly surveillance run and was subsequently declared inoperable. The immediate investigation determined that the 1 B RHR pump circiut breaker racking release handle had been placed in the "Trip Free" position instead of "Operational". The same 1 B RHR pump surveillance run was last completed satisfactorily on July 5, 2023, and there was no work on the 1 B RHR pump between July 5th and October 2nd that would have required manipulation of the component's breaker. The most likely cause was an inadvertent misposition of the wrong breaker during the 1 B Emergency Diesel (EOG) surveillance the morning of August 28, 2023. Corrective actions included placing the circuit breaker racking release handle in the "Operational" position and addressing human performance issues with the performance management process. The surveillance was completed satisfactorily and the 1 B RHR pump returned to operable status. This event is reportable under 10 CFR 50. 73(a)(2)(i)(B) for the 1 B RHR pump being inoperable for longer than allowed by Technical Specification 3.5.2. FNP Unit 2 was not affected during this event.
EVENT DESCRIPTION
I
- 2. DOCKET NUMBER
- 3. LER NUMBER I YEAR SEQUENTIAL REV NUMBER NO.
348 I 2023 I -I 1-0 002 At approximately 10:00 CDT on October 2, 2023, with Joseph M. Farley Nuclear Plant (FNP) Unit 1 in Mode 1 and 100 percent power, the 1 B residual heat removal (RHR) pump [EIIS: BP] failed to start on demand during the quarterly surveillance run and was subsequently declared inoperable. The immediate investigation determined that the 1 B RHR pump circuit breaker [EIIS/EEIS: BP/52] racking release handle had been placed in the "Trip Free" position instead of the "Operational" position. Within an hour of the failure to start, the circuit breaker racking release handle was placed in the "Operational" position allowing the charging springs to charge. The 1 B RHR pump quarterly surveillance run was completed satisfactorily at approximately 13:30 and the pump returned to operable status.
This same surveillance on the 1 B RHR pump was last run on July 5, 2023 and completed satisfactorily. There was no work on the 1 B RHR pump between July 5th and October 2nd that would have required manipulation of the component's breaker.
EVENT ANALYSIS
An investigation of this incident determined that the most likely cause of the 1 B RHR circuit breaker racking release handle being in the "Trip Free" position was due to human performance errors which resulted in the inadvertent mispositioning of the wrong breaker (1 B RHR pump breaker) during the 1 B Emergency Diesel (EDG) [EIIS: EK] surveillance the morning of August 28, 2023.
REPORTABILITY AND SAFETY ASSESSMENT
Based on the most probable cause of the 1 B RHR pump inoperability, there were no safety consequences since the 1A RHR pump was available from August 28th until October 2nd to perform the system's safety function. The event was within the analysis of the UFSAR Chapter 15, and is reportable under 10 CFR 50.73(a)(2)(i)(B) for the 1 B RHR pump being inoperable for longer than allowed by Technical Specification 3.5.2. FNP Unit 2 was not affected during this event.
CORRECTIVE ACTIONS PLANNED OR COMPLETED
- 1) The charging springs charged after the 1 B RHR pump circuit breaker racking release handle was placed in the "Operational" position. No damage was noted to the breaker or the pump.
- 2) Human performance errors have been addressed through the station's performance managment process.
PREVIOUS SIMILAR EVENTS
There were no events from the last three years with either the same or similar cause to this event. Page 2
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