IR 05000282/2015006

Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Inspection Report 05000282/2015006 and 05000306/2015006)

ML16060A325
Person / Time
Site:	Prairie Island
Issue date:	03/02/2016
From:	Louden P Division Reactor Projects III
To:	Davison K Northern States Power Co
References
IR 2015006
Download: ML16060A325 (6)

Text

UNITED STATES rch 2, 2016

SUBJECT:

ANNUAL ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2015006 AND 05000306/2015006)

Dear Mr. Davison:

On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Prairie Island 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, 2015, through December 31, 2015. 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. The NRC determined the performance at Prairie Island Unit 1 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., Green) safety significance, and all Performance Indicators (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 4th quarter of 2015 was within the Regulatory Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of one low-to-moderate (White) PI for Unplanned Scrams per 7000 critical hours. 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, following your notification to the NRC that you are ready. The purpose of the inspection is to provide assurance that: (1) the root causes and contributing causes of risk-significant performance issues are understood; (2) the extent of condition and extent of cause of risk-significant performance issues are identified; and (3) your corrective actions for risk-significant performance issues are sufficient to address the root and contributing causes and prevent recurrence. The enclosed inspection plan lists the inspections scheduled through December 31, 2017.

Routine inspections performed by resident inspectors are not included in the inspection plan.

The NRC inspection schedule includes a biennial inspection conducted in accordance with Inspection Procedure 71152, Problem Identification and Resolution. The inspections listed during the last 9 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.

In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. This Order requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. This Order requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. The audit was completed for Prairie Island Units 1 and 2, and the information gathered will aid staff in development of the Safety Evaluation for the site. After the NRC staff receives the Final Compliance letter for the site, the Final Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing Temporary Instruction 191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.

In accordance with 10 CFR 2.390 of the NRCs 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 (PARS) component of NRC's document system (ADAMS). ADAMS is 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/

Patrick L. Louden, Director Division of Reactor Projects Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure:

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