IR 05000282/2012406
| ML12286A407 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/12/2012 |
| From: | Reynolds S Division of Reactor Safety III |
| To: | Sorensen J Northern States Power Co |
| References | |
| EA-11-203 IR-12-406 | |
| Download: ML12286A407 (3) | |
Text
October 12, 2012
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2; NRC SUPPLEMENTAL INSPECTION REPORT 05000282/2012406; 05000306/2012406
Dear Mr. Sorensen:
On August 31, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff completed a supplemental inspection at your Prairie Island Nuclear Generating Plant. The enclosed inspection report documents the inspection results, which were discussed at the exit meeting on August 31, 2012, with Mr. J. Molden and other members of your staff. During this meeting, R. Skokowski, the Acting Region III DRS Deputy Director, discussed the associated performance deficiencies and corrective actions with your staff, which fulfills NRC policy for a regulatory performance meeting.
In accordance with the NRC Reactor Oversight Process Action Matrix, this supplemental inspection was performed to follow-up on a performance issue which occurred in the fourth quarter of 2011. The issue was previously documented and assessed in NRC Inspection Report 05000282/2011405; 05000306/2011405. The NRC was informed of your readiness for the inspection on May 16, 2012.
The objectives of this supplemental inspection were to determine whether or not: (1) the root causes and contributing causes for the significant issues were understood; (2) the extent of condition and the extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.
All inspection objectives described in Inspection Procedure 95001 were completed during the inspection. As a result, Violation 05000282/2011405-01; 05000306/2011405-01 is closed.
Based on the results of this inspection, no findings were identified.
Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. 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/
Steven A. Reynolds, Director Division of Reactor Safety
Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60
Nonpublic Enclosure: Inspection Report 05000282/2012406; 05000306/2012406
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 K. Riemer, RIII N. Shah, RIII J. Lara, RIII
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