IR 05000247/2016009

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Davis-Besse Nuclear Power Station, Unit 1, Revision 31 to Updated Final Safety Analysis Report, Drawing E-0058B, Rev 12, Sheet 0015A
ML16326A064
Person / Time
Site: Davis Besse, Indian Point Cleveland Electric icon.png
Issue date: 11/21/2016
From:
Bechtel Company, FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17039A594 List: ... further results
References
L-16-322 E-0058B, Rev 12
Download: ML16326A064 (22

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Accession Number:ML17045A331
Estimated Page Count:1)
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Text

November 21, 2016

Mr. Anthony Site Vice President Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB Buchanan, NY 10511-0249

SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT 3 - SUPPLEMENTAL INSPECTION REPORT 05000286/2016009 AND ASSESSMENT FOLLOW-UP LETTER

Dear Mr. Vitale:

On October 13, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection using Inspection Procedure (IP) 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," at your Indian Point Nuclear Generating (Indian Point) Unit 3. On October 13, 2016, the NRC inspection team discussed the results of this inspection with Mr. John Ferrick and other members of your staff. The results of this inspection are documented in the enclosed report.

In the fourth quarter of 2015, your staff reported an unplanned automatic reactor trip on December 14, 2015, that caused the "Unplanned Scrams per 7,000 Hours Critical" performance indicator (PI) to cross a threshold from Green to White. Based on your report, the NRC assigned a White PI Action Matrix input to the Initiating Events cornerstone in the fourth quarter of 2015.

In response to this Action Matrix input, the NRC informed you in the Annual Assessment Letter, dated March 2, 2016, that a supplemental inspection under IP 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," would be required. On July 11, 2016, you informed the NRC that Indian Point Unit 3 was ready for the supplemental inspection.

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 actions were sufficient to address and prevent repetition of the root and contributing causes.

The inspection consisted of examination of activities conducted under your license as they relate to safety, compliance with the Commission's rules and regulations, and the conditions of your operating license. Based on the results of this inspection, the NRC concluded that Entergy performed a satisfactory evaluation of the White PI and met the inspection objectives. Entergy's evaluation of the root and contributing causes associated with four unplanned reactor scrams was generally appropriate. Entergy appropriately identified the root cause to include decision making regarding single point vulnerabilities that led to reactor scrams. Overall, Entergy satisfactorily identified the individual and collective performance issues associated with the White PI and has appropriate corrective actions either implemented or planned to address these issues. The NRC has determined that completed or planned corrective actions were sufficient to address the performance that led to the White PI.

NRC inspectors documented one self-revealing finding of very low safety significance (Green) in this report. The finding did not involve a violation of NRC requirements. If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U. S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC, 20555-0001; with copies to the Regional Administrator, Region I; and the NRC Resident Inspectors at Indian Point.

Based on the guidance in Inspection Manual Chapter 0305, "Operating Reactor Assessment Program," and the results of this inspection, the White PI will be closed and Indian Point Unit 3 will transition from the Regulatory Response Column of the NRC's Action Matrix to the Licensee Response Column as of the date of the cover letter to this report.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,/RA/ Eugene M. DiPaolo, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket No. 50-286 License No. DPR-64

Enclosure:

Inspection Report 05000286/2016009

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