IR 05000245/2016404

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Millstone Power Station - Problem Identification and Resolution Sample Inspection Report 05000336/2016404 and 05000423/2016404
ML16210A292
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 07/27/2016
From: Christopher Cahill
Engineering Region 1 Branch 3
To: Heacock D A
Dominion Resources
Cahill C G
References
IR 2016404
Download: ML16210A292 (4)


Text

D. July 27, 2016

Mr. David President and Chief Nuclear Officer Dominion Resources 5000 Dominion Blvd.

Glen Allen, VA 23060-6711

SUBJECT: MILLSTONE POWER STATION - PROBLEM IDENTIFICATION AND RESOLUTION SAMPLE INSPECTION REPORT 05000336/2016404 AND 05000423/2016404

Dear Mr. Heacock:

On July 14, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a security-related Problem Identification and Resolution inspection at your Millstone Power Station (Millstone),

Units 2 and 3. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on July 14, 2016, with Ms. Lori Armstrong, Director, Station Recovery, and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed station personnel.

Based on the results of this inspection, one finding of very low safety significance (Green) was identified. This finding was also determined to be a violation of NRC requirements. However, because of its very low safety significance and because it was entered into your corrective action program, the NRC is treating this finding as a non-cited violation (NCV) consistent with Section 2.3.2 of the NRC Enforcement Policy.

If you contest any NCV in this report, you should provide a written response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington D.C. 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Senior Resident Inspector at Millstone. In addition, if you disagree with the cross-cutting aspect assigned to this finding, you should provide a written response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I, and the NRC Senior Resident Inspector at Millstone.

Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, the transmittal document is decontrolled. In accordance with Title 10 of the Code of Federal Regulation (10 CFR) 2.390 of the NRC's "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 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.

Sincerely,/RA/ Christopher G. Cahill, P.E., Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosure:

Inspection Report 05000336/2016404 and 05000423/2016404

w/Attachment:

Supplemental Information cc w/o encl; w/o OUO-SRI: Distribution via ListServ cc w/ encl; w/ OUO-SRI: M. Brown, Security Department Manager J. Semancik, Director, CT Dept. of Energy and Environmental Protection