IR 05000440/2018040

Perry Nuclear Power Plant - NRC Supplemental Inspection Report 05000440/2018040 and Assessment Follow-Up Letter

ML18086B212
Person / Time
Site:	Perry
Issue date:	03/27/2018
From:	Billy Dickson NRC/RGN-III/DRP/B5
To:	Hamilton D FirstEnergy Nuclear Operating Co
References
EA-17-043 IR 2018040
Download: ML18086B212 (17)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, ILLINOIS 60532-4352 March 27, 2018 EA-17-043

Mr. David Hamilton Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097

SUBJECT: PERRY NUCLEAR POWER PLANT-NRC SUPPLEMENTAL INSPECTION REPORT 05000440/2018040 AND ASSESSMENT FOLLOW-UP LETTER

Dear Mr. Hamilton:

The U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection using Inspection Procedure 95001, "Supplemental Inspec tion Response To Action Matrix Column 2 Inputs," at your Perry Nuclear Power Plant. On February 15, 2018, the NRC discussed the results of this inspection and the implementation of your corrective actions with Mr. Frank Payne and other members of your staff in an exit Meeting. On February 16, 2018, the NRC discussed the causes and your corrective actions identified as a result of the WHITE finding, and the criteria required for returning to the Licensee Response Column of the Action Matrix with Mr. Frank Payne in a Regulatory Performance Meeting. The results of this inspection are documented in the enclosed report. By letter dated August 24, 2017, (ADAMS ML17236A187), the U.S. Nuclear Regulatory Commission (NRC) informed you that as a result of a White (low-to-moderate safety significance) finding in the Mitigating Systems Cornerstone that the NRC assessed Perry Nuclear Power Plant performance to be in the Regulatory Response Column of the Reactor Oversight Process (ROP) Action Matrix, effective the second quarter of 2017. In the same letter, the NRC informed you of our intent to perform a supplemental inspec tion using Inspection Procedure 95001 upon notification of your readiness for the inspection. By letter dated October 31, 2017, we were notified by your staff that you were ready for the NRC to conduct our supplemental inspection to review the actions taken to address the White finding. The NRC performed this inspection to review your station's actions in response to a White finding in the Mitigating System cornerstone which was documented in NRC Inspection Report 05000440/2017009 (ML17156A750). The finding involved the failure to evaluate the effects of voltage suppression diode failure on the Emergency Diesel Generator (EDG) control circuit, which was a component subject to the requirements of Title 10 of the Code of Federal Regulations (CFR) Part 50, Appendix B. Specifically, FirstEnergy failed to consider the effect of a shorted diode on the control circuitry of the EDG, and, as a result, failed to recognize that installation of voltage suppression diodes across control relays, with no mitigation for diode failure, was not suitable for the EDG control circuit. This introduction of new components (diodes) into the control circuitry resulted in the eventual failure of the EDG control circuit, thereby rendering the EDG inoperable and unable to start. The NRC determined that the completed or planned corrective actions were sufficient to address the performance issue that led to the White finding previously described and were prioritized commensurate with the safety significance of the issue. In addition, the NRC determined that the root cause evaluation was conducted to a level of detail commensurate with the significance of the problem and reached reasonable conclusions as to the root and contributing causes of the event. No finding or violations were documented. After reviewing Perry Nuclear Power Plant's performance in addressing the White finding subject of this Inspection Procedure 95001, the NRC concluded your actions met the objectives of the inspection. Therefore, in accordance with the guidance in Inspection Manual

Chapter (IMC) 0305, "Operating Reactor Assessment Program," the White finding will only be considered in assessing plant performance for a total of four quarters. As a result, the NRC determined the performance at Perry Nuclear Power Plant to be in the Licensee Response Column of the ROP Action Matrix as of April 1, 2018.

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 at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,/RA/

Billy Dickson, Chief

Branch 5 Division of Reactor Projects Docket No. 50-440 License No. NPF-58

Enclosure:

Inspection Report 05000440/2018040 cc: Distribution via LISTSERV