IR 05000282/2014403

Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1 - 7 Inspection Report 05000282/2014403; 05000306/2014403 - Cover Letter

ML14190B019
Person / Time
Site:	Prairie Island
Issue date:	07/08/2014
From:	Robert Daley Engineering Branch 3
To:	Davison K Northern States Power Co
Alal Dahbur
References
IR-14-403
Download: ML14190B019 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION uly 8, 2014

SUBJECT:

PRAIRE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 TEMPORARY INSTRUCTION 2201/004, INSPECTION OF IMPLEMENTATION OF INTERIM CYBER SECURITY MILESTONES 1 - 7 INSPECTION REPORT 05000282/2014403; 05000306/2014403 - COVER LETTER

Dear Mr. Davison:

On June 6, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2. The inspection covered the interim cyber security Milestones 1 - 7 of the security cornerstone. The enclosed inspection report documents the inspection results, which were discussed on June 6, 2014, with you and other members of your staff.

The inspection examined activities conducted under your license as they relate to cyber security and compliance with the Commissions rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Four NRC-identified finding of very low significance (Green) were identified during this inspection.

The findings were determined to involve violations of NRC requirements. The NRC is treating these violations as Non-Cited Violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy. However, in accordance with the Security Issues Forum (SIF) Charter, the NRC may exercise enforcement discretion during inspection of the interim cyber security measures for licensees who demonstrate a good-faith interpretation and attempt to implement Milestones 1 - 7. This discretion applies to licensees who have tried to implement the new requirements, but failed to be in full compliance. Before discretion is considered or granted for any issue, licensees must accept the finding, put the finding into their Corrective Action Program (CAP), and take appropriate corrective action once identified.

These issues were discussed and reviewed during the SIF Meeting conducted on June 18, 2014.

The results of the SIF Panel review concluded that although these issues constituted violations of your facility operating license (FOL) and Title 10, Code of Federal Regulations (CFR), Part 73, Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. Section 54, Protection of Digital Computer and Communication Systems and Networks, the NRC is not pursuing enforcement action because of your good-faith attempt to interpret and implement Milestones 1 - 7 and because of your prompt corrective actions to enter these issues into your CAP. Upon completion of all corrective actions, you are requested to provide written notification to the NRCs regional office as to the method and date of closure for the identified issue(s).

In accordance with Title 10, Code of Federal Regulations (CFR) "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 System (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 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/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No(s).: 50-282; 50-306 License No(s).: DPR-42; DPR-60 Nonpublic Enclosure:

Inspection Report 05000282/2014403; 05000306/2014403 w/Attachment: Supplemental Information cc w/encl: J. Corwin, Prairie Island Nuclear Generating Plant, Security Manager B. Westreich, NSIR R. Felts, NSIR S. Coker, NSIR J. Rogge, RI S. Shaeffer, RII J. Dixon, RIV N. Coleman, OE