RA-23-0096, Post Accident Monitoring (PAM) Instrumentation Report

Post Accident Monitoring (PAM) Instrumentation Report

ML23102A181
Person / Time
Site:	Brunswick
Issue date:	04/12/2023
From:	Dewire M Duke Energy Progress
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RA-23-0096
Download: ML23102A181 (1)

Text

Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 April 12, 2023 Serial: RA-23-0096 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 2 Renewed Facility Operating License No. DPR-62 Docket No. 50-324 Post Accident Monitoring (PAM) Instrumentation Report Ladies and Gentlemen:

Duke Energy Progress, LLC (Duke Energy), is providing this Post Accident Monitoring (PAM)

Instrumentation Report in accordance with Brunswick Steam Electric Plant, Unit No. 2, Technical Specification (TS) 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report. As required by TS 5.6.6, this report is being submitted within 14 days following entry into TS Limiting Condition for Operation (LCO) 3.3.3.1, Post Accident Monitoring (PAM)

Instrumentation, Condition B.

At 21:30 on March 13, 2023, TS LCO 3.3.3.1, Post Accident Monitoring (PAM)

Instrumentation, Condition A, was entered as a result of one of the required Drywell Area Radiation instrumentation channels being inoperable. TS LCO 3.3.3.1, Condition A, requires the required channel be restored to operable status within 30 days. Troubleshooting determined that the inoperability is likely a result of an issue with the instrumentation connections located in the drywell. Repair activities would require Unit 2 be shutdown. As a result, operability was not restored within 30 days per TS LCO 3.3.3.1, Condition A, and Condition B was entered, requiring this report.

Duke Energy plans to complete repair activities to restore operability of the required Drywell Area Radiation instrumentation channel during the next Unit 2 refueling outage, scheduled for March 2025. Until operability is restored, the alternate Drywell Area Radiation instrumentation channel can be utilized for monitoring along with the Containment Atmosphere Particulate, Radio-Iodine, and Noble Gas Radiation Monitors. In addition, alternate indicators for monitoring for fuel cladding damage remain available, including reactor water level, reactor water sample analysis, Steam Jet Air Ejector radiation monitors, and main steam line radiation detectors.

fa DUKE

~ ENERGY

U.S. Nuclear Regulatory Commission Page 2 of 2 This document contains no regulatory commitments.

Please refer any questions regarding this submittal to Mr. Stephen Yodersmith, Brunswick Regulatory Affairs, at (910) 832-2568.

Sincer~_.__--

Mark R. DeWire Manager - Nuclear Support Services Brunswick Steam Electric Plant SBY/sby cc:

Ms. Laura Dudes, NRC Regional Administrator, Region II Mr. Luke Haeg, NRC Project Manager Mr. Gale Smith, NRC Senior Resident Inspector Chair - North Carolina Utilities Commission