IR 05000346/2013408
| ML13354B795 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/19/2013 |
| From: | Richard Skokowski Plant Support Branch II |
| To: | Lieb R FirstEnergy Nuclear Operating Co |
| Joseph Maynen | |
| References | |
| EA-12-179 IR-13-408 | |
| Download: ML13354B795 (5) | |
Text
December 19, 2013
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 NRC SUPPLEMENTAL INSPECTION REPORT AND ASSESSMENT FOLLOWUP LETTER 05000346/2013408
Dear Mr. Lieb:
On August 10, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection activity at your Davis-Besse Nuclear Power Station, Unit 1. Based on the results of this inspection, documented in NRC Inspection Report 05000346/2012403 on September 7, 2012, and the final significance determination documented in NRC Inspection Report 05000346/2012405 on November 8, 2012, the NRC assigned a finding Action Matrix input to the security cornerstone in the third quarter of 2012. In response to this Action Matrix input, the NRC informed you that a supplemental inspection would be required. On September 6, 2013, you informed the NRC that the station was ready for the supplemental inspection.
On November 7, 2013, the NRC completed the supplemental inspection pursuant to Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area. The enclosed inspection report documents the inspection results, which were discussed on November 7, 2013. On December 12, 2013, Mr. R. Skokowski, Chief, Region III Division of Reactor Safety, Plant Support Branch, discussed the associated performance deficiencies and implementation of your corrective actions with you and other members of your staff, which fulfills the NRC policy of a regulatory performance meeting.
The NRC performed this supplemental inspection to determine if: (1) the root and contributing causes for the significant issues were understood; (2) the extent of condition and extent of cause for the identified issues were understood; and (3) your completed or planned corrective
Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. actions were sufficient to address and prevent repetition of the root and contributing causes.
The NRC has determined that completed or planned corrective actions were sufficient to address the performance that led to the finding. As a result, the NRC concluded that the objectives of the inspection were met and that Violation 05000346/2013405-01 will be closed.
Therefore, the performance issue will not be considered as an Action Matrix input as of the date of this supplemental inspection report and assessment follow-up letter.
The NRC inspector did not identify any findings or violations of more than minor significance.
As a result of its continuous review of plant performance, the NRC updated its assessment of Davis-Besse Nuclear Power Station, Unit 1. The NRCs evaluation consisted of a review of performance indicators and inspection results. This letter informs you of the NRCs assessment of your facility. This letter supplements, but does not supersede, the annual assessment letter issued on March 4, 2013.
After reviewing Davis-Besse Nuclear Power Stations performance in addressing the greater-than-green finding subject of this Inspection Procedure (IP), the NRC concluded your actions met the objectives of IP 95001. Therefore, in accordance with the guidance in Inspection Manual Chapter (IMC) 0305, Operating Reactor Assessment Program, the greater-than-green finding will only be considered in assessing plant performance for at least four quarters. As a result, the NRC determined the performance at Davis-Besse Nuclear Power Station will be in the Licensee Response Column of the Reactor Oversight Process Action Matrix as of the date of this supplemental inspection report and assessment follow-up letter.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information-Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely,
/RA/
Richard A. Skokowski, Chief Plant Support Branch Division of Reactor Safety
Docket No. 50-346 License No. NPF-3
Nonpublic Enclosure: Inspection Report 05000346/2013408;
w/Attachment: Supplemental Information
cc w/encl:
S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI B. Desai, RII M. Haire, RIV M. Bear, State Liaison Officer, Ohio Emergency Management Agency
cc w/o encl:
Distribution via ListServ'