IR 05000346/2021006

Annual Assessment Letter for Davis-Besse Nuclear Power Station, Unit 1 (Report 05000346/2021006)

ML22055B117
Person / Time
Site:	Davis Besse
Issue date:	03/02/2022
From:	Julio Lara NRC/RGN-III/DRP/B2
To:	Tony Brown Energy Harbor Nuclear Corp
Shared Package
ML21362A675	List: IR 05000346/2021006 ML22159A335 ML22159A338 ML22178A195 ML22178A231
References
IR 2021006
Download: ML22055B117 (5)

Text

March 2, 2022

SUBJECT:

ANNUAL ASSESSMENT LETTER FOR DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 (REPORT 05000346/2021006)

Dear Mr. Brown:

The NRC has completed its end-of-cycle performance assessment of the Davis-Besse Nuclear Power Station, Unit 1, reviewing performance indicators (PIs), inspection results, and enforcement actions from January 1, 2021, through December 31, 2021. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. The NRC concluded that overall performance at your facility preserved public health and safety. The baseline inspection program was completed at your facility as defined in Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program - Operations Phase.

The NRC determined the performance at Davis-Besse Nuclear Power Station, Unit 1, during the most recent quarter was within the Regulatory Response Column (Column 2), the second highest performance column of the NRCs Reactor Oversight Process (ROP) Action Matrix.

This conclusion was based on one or more greater-than-Green inspection findings (or PIs) in the Security cornerstone, originating in the third quarter of 2021 (ML22031A171); and a single inspection finding having low-to-moderate safety significance (i.e., White) in the Mitigating Systems cornerstone, originating in the fourth quarter of 2021 (ML21356A058). Prior to this transition to Column 2 of the Action Matrix in the third quarter of the 2021 assessment period, plant performance was within the Licensee Response Column (Column 1).

Therefore, in addition to ROP baseline inspections, the NRC plans to conduct one or more supplemental inspection(s), at its discretion, in accordance with Inspection Procedure (IP) 95001, Supplemental Inspection Response to Action Matrix Column 2 (Regulatory Response)

Inputs. This inspection procedure is conducted to provide assurance that the root cause and contributing cause of risk significant performance issues are understood, the extent of condition and the extent of cause are identified, and the corrective actions are sufficient to prevent recurrence. This inspection(s) will be scheduled when you notify the NRC of your readiness.

Although plant performance was within the Regulatory Response Column, the NRC has not yet finalized the characterization of Apparent Violation (AV)05000346/2021050-04, Failure to Inspect Emergency Diesel Generator Selector Switch. The final determination may affect the NRCs assessment of plant performance and the enclosed inspection plan. The enclosed inspection plan lists the inspections scheduled through December 31, 2023.

The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last twelve months of the inspection plan are tentative and may be revised. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.

In response to the COVID-19 public health emergency (PHE), the NRC adjusted inspection plans and schedules in order to safeguard the health and safety of both NRC and licensee staff while still effectively implementing the ROP. While the PHE continues, overall conditions throughout the country support performance of our inspection and oversight activities to return to normal onsite presence by our resident and region-based inspectors and completion of nominal baseline inspection samples. We continue to monitor site-specific conditions and as discussed in our November 2, 2021, memo, Implementation of Inspection Programs Following Re-Entry from the Public Health Emergency for the Reactor Safety Program (ML21295A302), it may be necessary to alter how and when we perform our inspection and oversight activities as we balance the importance of protecting the health and safety of our staff with the need to conduct effective oversight that supports the NRCs critical safety mission. For inspections requiring extensive coordination with offsite organizations, such as evaluated emergency preparedness exercises, NRC guidance and frequently asked questions for security and emergency preparedness can be found here: https://www.nrc.gov/about-nrc/covid-19/security-ep/. Similarly, the NRC has developed guidance if force-on-force inspections cannot be completed as scheduled due to an emergency, such as the COVID-19 PHE. These changes help ensure the health and safety of both NRC and licensee staff while maintaining the NRCs important safety and security mission during the COVID-19 PHE. The attached inspection plan is accurate on the date of issuance but remains subject to change based on approval of potential exemption requests or other changes needed due to changing conditions in the COVID-19 PHE. NRC staff will contact your appropriate regulatory affairs staff in order to coordinate inspection planning and scheduling.

The NRC plans to perform Inspection Procedure (IP) 71003, Post-Approval Site Inspection for License Renewal at your facility. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Please contact Mr. Billy Dickson at (630) 829-9827 with any questions you have regarding this letter.

Sincerely,

/RA/

Julio F. Lara, Director Division of Reactor Projects Region III Docket Nos. 05000346 and 07200014 License No. NPF-3 Enclosure:

Inspection Plan cc: Distribution via LISTSERV