IR 05000282/2008006

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IR 05000282-08-006, (Drs), IR 05000306-08-006, (Drs), on 05/12/2008 - 07/09/2008 for Prairie Island, Units 1 and 2, Ti 2515/171 Verification of S,Ite Specific Implementation of B.5.b Phase 2 and 3, Mitigating Strategies
ML082110391
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 07/23/2008
From: Hironori Peterson
Operations Branch I
To: Wadley M
Nuclear Management Co
References
IR-08-006
Download: ML082110391 (5)


Text

uly 23, 2008

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 TI 2515/171 VERIFICATION OF SITE SPECIFIC IMPLEMENTATION OF B.5.b PHASE 2 AND 3 MITIGATING STRATEGIES INSPECTION REPORT NO. 05000282/2008006(DRS); 5000306/2008006(DRS)

Dear Mr. Wadley:

On July 9, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed a team inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2. The enclosed report documents the results of the inspection, which were initially discussed on May 16, 2008, and subsequently exited on July 9, 2008, with you and other members of your staff.

The inspection examined activities conducted under your license as they relate to the implementation of B.5.b Phase 2 and 3 mitigating strategies, your compliance with the Commission=s rules and regulations, and with the conditions of your operating licenses. Within these areas, the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personnel.

Based on the results of this inspection, one NRC-identified finding of very low safety significance was identified. However, because this violation was of very low safety significance and because it was entered into your corrective action program, the NRC is treating the issue as a Non-Cited Violation in accordance with Section VI.A.1 of the NRCs Enforcement Policy. The team concluded that, in general, you had implemented the Site Specific B.5.b Phase 2 and 3 Mitigating Strategies as described in your submittals and the associated Safety Evaluation Report.

Enclosures Contains Sensitive Unclassified Non-Safeguards Information. Upon separation, this page is decontrolled. If you contest the finding or the subject or severity of the Non-Cited Violation in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001, with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector Office at the 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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the sensitive information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letters enclosure will not be available for public inspection.

Sincerely,

/RA/

Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Nonpublic Enclosure: Inspection Report 05000282/2008006(DRS);

05000306/2008006(DRS)

w/Attachment: Supplemental Information cc w/encl: D. Nelson, NRR/DPR/PSPB E. Bowman, NRR/DPR/PSPB DISTRIBUTION See next page