IR 05000346/2016408

NRC Supplemental Inspection Report 05000346/2016408 and Assessment Follow-up Letter (Cover Letter Only)

ML16223A877
Person / Time
Site:	Davis Besse
Issue date:	08/10/2016
From:	O'Brien K Division of Reactor Safety III
To:	Boles B FirstEnergy Nuclear Operating Co
References
IR 2016408
Download: ML16223A877 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ust 10, 2016

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION - NRC SUPPLEMENTAL INSPECTION REPORT 05000346/2016408 AND ASSESSMENT FOLLOW-UP LETTER

Dear Mr. Boles:

On June 30, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff completed a supplemental inspection, at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection results, which were discussed at the exit meeting, on June 30, 2016, with Mr. D. Saltz and other members of your staff. During this meeting, members of your staff discussed the associated performance deficiency and corrective actions with Messrs. S. Orth and M. Ziolkowski, which fulfills NRC policy for a regulatory performance meeting.

In accordance with the NRC Reactor Oversight Process (ROP) Action Matrix, this supplemental inspection was performed to follow-up on a performance issue that was identified in the fourth quarter of 2015. The issue was previously documented and assessed in NRC Inspection Report (IR) 05000346/2015408 and NRC letter dated January 25, 2016. The NRC was informed of your readiness for the inspection on June 17, 2016.

The objectives of this supplemental inspection were to determine whether or not: (1) the root-causes and contributing causes for the significant issues were understood; (2) the extent of condition and the extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.

After reviewing Davis-Besse Nuclear Power Station performance in addressing the Greater-Than-Green finding that was the subject of this inspection, the NRC concluded that your actions met the objectives. Therefore, in accordance with the guidance in Inspection Manual Chapter 0305, Operating Reactor Assessment Program, this Greater-Than-Green finding will only be considered in assessing plant performance through the completion of the third quarter 2016.

In the letter dated April 26, 2016, the NRC determined the Unplanned SCRAMS with Complications performance indicator had crossed the green-to-white threshold, effective the end of the first quarter of 2016. Therefore, Davis-Besse will remain in the Regulatory Response Enclosure contains Sensitive Unclassified Non-Safeguards Information.

When separated from enclosure, this transmittal document is decontrolled. Column of the ROP action matrix. A separate letter will communicate the NRCs assessment of Davis-Besses performance following the completion of the supplemental inspection to address the performance indicator.

No findings were identified during this inspection.

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/

Kenneth G. OBrien, Director Division of Reactor Safety Docket No. 50-346 License No. NPF-3 Nonpublic Enclosure:

IR 05000346/2016408 cc: M. Bear, State Liaison Officer Ohio Emergency Management Agency cc w/o encl: Distribution via LISTSERV