IR 05000282/2013001

Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2(Report 05000282/2013001; 05000306/2013001)

ML14063A297
Person / Time
Site:	Prairie Island
Issue date:	03/04/2014
From:	Boland A Division Reactor Projects III
To:	Davison K Northern States Power Co
References
IR-13-001
Download: ML14063A297 (6)

Text

UNITED STATES rch 4, 2014

SUBJECT:

ANNUAL ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2013001; 05000306/2013001)

Dear Mr. Davison:

On February 12, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Prairie Island Nuclear Generating Plant, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2013 through December 31, 2013. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.

The NRC determined that overall, Prairie Island Unit 1 operated in a manner that preserved public health and safety and met all cornerstone objectives. Prairie Island Unit 1 began the assessment period in the Regulatory Response Column of the NRCs Reactor Oversight Process (ROP) for a WHITE Finding in Emergency Preparedness for a failure to maintain ability to classify emergency action levels. In a letter dated August 29, 2013, the NRC notified Prairie Island that the NRC had completed its supplemental inspection and that Unit 1 returned to the Licensee Response Column as of the fourth quarter of 2013. The NRC determined the performance of Unit 1 during the most recent quarter was within the Licensee Response Column of the NRCs ROP Action Matrix, because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility.

The NRC determined the performance at Prairie Island Unit 2 during the most recent quarter was within the Regulatory Response Column of the NRCs ROP Action Matrix, because of one low-to-moderate safety significant (White) PI for Emergency Alternating Current Power Systems in the Mitigating Systems Performance Index.

On November 25, 2013, your staff notified the NRC of your readiness for us to conduct a supplemental inspection to review the actions taken to address the performance issues.

However, on January 31, 2014, your staff requested the NRC postpone the planned inspection due to questions regarding corrective action effectiveness. Therefore, in addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, after you notify the NRC of your readiness.

As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised beginning in calendar year (CY) 2014. New cross-cutting aspects identified in CY 2014 will be coded under the latest revision to Inspection Manual Chapter (IMC) 0310. Cross-cutting aspects identified in the last six months of 2013 using the previous terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310. The revised cross-cutting aspects will be evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305 starting with the CY 2014 mid-cycle assessment review.

The enclosed inspection plan lists the inspections scheduled through June 30, 2015. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the mid-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.

We also plan on conducting Temporary Instruction 2515/189 Inspection to Determine Compliance of Dynamic Restraint (Snubber) Program with 10 CFR 50.55a and Inspection Procedure 71003 Post-Approval Site Inspection For License Renewal.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure, 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). Please contact Kenneth Riemer at 630-829-9628 with any questions you have regarding this letter.

Sincerely,

/RA/

Anne T. Boland, Director Division of Reactor Projects Docket Nos. 50-282; 50-306; and 72-010 License Nos. DPR-42; DPR-60; and SNM-2506 Enclosure:

Prairie Island Nuclear Generating Plant Inspection/Activity Plan cc w/encl: Distribution via ListServTM