IR 05000282/2014001

Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2, (Report 05000282/2014001 and 05000306/2014001)

ML15063A038
Person / Time
Site:	Prairie Island
Issue date:	03/04/2015
From:	Boland A T Division Reactor Projects III
To:	Davison K Northern States Power Co
References
IR 2014001
Download: ML15063A038 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532

-4352 March 4, 2015 Mr. Kevin Davison Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT: ANNUAL ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2014001 AND 05000306/2014001)

Dear Mr. Davison:

On February 11, 2015, 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, 2014 through December 31, 2014. This letter informs you of the NRC's 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 NRC

's Reactor Oversight Process (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 for Unit 1 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 NRC

's 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. As described in Inspection Report 05000306/2014009 (ML14323A020

), the NRC completed the required supplemental inspection and Prairie Island Unit 2 transition ed back to the Licensee Response Column of the ROP Action Matrix on November 18, 2014. With the closure of this White PI, all inspection findings having very low safety significance and all other PI's within the nominal expected range, the NRC will conduct ROP baseline inspections for Unit 2 at your facility

. In the mid

-cycle assessment letter dated September 2, 2014 (ML14245A201), the NRC opened a substantive cross

-cutting issue (SCCI) associated with the aspect of Documentation (H.7). This assessment letter stated that the SCCI will remain open until the number of findings with a cross-cutting aspect of H.7 is reduced, the corrective actions taken to mitigate the cross

-cutting theme prove effective, and sustained performance improvement is observed in the human performance area.

During the current assessment period, the number of findings with H.7 assigned as the cross

-cutting aspect has been reduced and no longer meets the definition of cross-cutting theme as described in IMC 0305

, "Operating Reactor Assessment Program," dated November 20, 2014. Specifically, a cross

-cutting theme exists if there are four or more findings having the same cross

-cutting aspect. To address the SCCI, your staff performed a root cause evaluation and developed corrective actions.

However, as of the end of the assessment period, not all of the proposed corrective actions were completed and no effectiveness review of those completed corrective actions has been performed.

Therefore, the SCCI will remain open until the corrective actions taken to mitigate the cross

-cutting theme prove effective and sustained performance improvement is observed in the human performance area. This is the second consecutive assessment letter documenting this SCCI.

The NRC will continue to monitor your staff's effort and progress in addressing the SCCI by evaluating your corrective action program, the root cause evaluation for the SCCI, and performance improvement initiatives to adequately assess if positive results are obtained.

The enclosed inspection plan lists the inspections scheduled through June 30, 2016. 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.

As stated in the inspection plan, from August 3, to September 4, 2015, the NRC plans to perform the Component Design Basis Inspection.

Additionally, an NRC audit of licensee efforts towards compliance with Order EA

-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," and Order EA

-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation" is ongoing for various sites.

The audit includes an onsite visit for the NRC staff to evaluate mitigating strategies as described in the licensee submittals, and to receive and review information relative to associated open items. This onsite audit will occur prior to the first unit at the site achieving compliance with the Orders and the audit will aid NRC staff in developing a final Safety Evaluation for the site.

The audit at your site has been scheduled for the week of May 11, 2015

. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy

of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the 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).

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 License Nos.

DPR-42; DPR-60

Enclosure:

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