IR 05000282/2013405

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IR 05000282-13-405; 05000306-13-405; 07/29/2013 - 08/01/2013; Prairie Island Nuclear Generating Plant; Routine Security Baseline Inspection; Equipment Performance, Testing, and Maintenance (71130.04) (Cover Letter Only)
ML13252A304
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 09/06/2013
From: Richard Skokowski
Plant Support Branch II
To: Jeffery Lynch
Northern States Power Co
References
IR-13-405
Download: ML13252A304 (4)


Text

UNITED STATES ber 6, 2013

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2; NRC SECURITY BASELINE INSPECTION REPORT 05000282/2013405; 05000306/2013405

Dear Mr. Lynch:

On August 1, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Prairie Island Nuclear Generating Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on August 1, 2013, with Mr. J. Anderson and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.

One NRC-identified finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) was identified during this inspection.

The deficiency was promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspector left the area. This finding was determined to involve a violation of NRC requirements. Further, two licensee-identified violations, which were determined to be of very low security significance, are listed in this report. The NRC is treating these violations as Non-Cited Violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violations or significance of these NCVs, you should provide a 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 DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Prairie Island Nuclear Generating Plant.

Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. One cross-cutting aspect was assigned to a finding in the area of Human Performance, Work Practices H.4(c), because the licensee failed to ensure supervisory and management oversight of work activities, including contractors, such that nuclear safety is supported.

If you disagree with the cross-cutting aspect assignment 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 Regional Administrator, Region III; and the NRC Resident Inspector at Prairie Island Nuclear Generating Plant.

In accordance with 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 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 NRCs 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/ By David E. Hills Acting For/

Richard A. Skokowski, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Nonpublic Enclosure: Inspection Report 05000282/2013405; 05000306/2013405 w/Attachment: Supplemental Information cc w/encl: S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI B. Desai, RII M. Haire, RIV cc w/o encl: Distribution via ListServ'