IR 05000263/2015006

Annual Assessment Letter for Monticello Nuclear Generating Plant (Inspection Report 05000263/2015006)

ML16060A301
Person / Time
Site:	Monticello
Issue date:	03/02/2016
From:	Pederson C D NRC/RGN-III
To:	Gardner P A Northern States Power Co
References
IR 2015006
Download: ML16060A301 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I I I 24 43 WARRENVILLE RD

. SUITE 2 1 0 LISLE , I L 60532-4352 Mr. Peter Site Vice President Monticello Nuclear Generating Plant Northern States Power Company, Minnesota 2807 West County Road 75 Monticello, MN 55362

-9637 SUBJECT: ANNUAL ASSESSMENT LETTER FOR MONTICELLO NUCLEAR GENERATING PLANT (REPORT 05000 263/20 15006)

Dear Mr. Gardner:

On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Monticello Nuclear Generating Plant. 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 NRC's assessment of your facility during this period and its plans for future inspections at your facility.

The NRC determined that overall Monticello Nuclear Generating Plant operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance of Monticello Nuclear Generating Plant 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 at your facility.

In its Mid

-Cycle Assessment letter dated September 1, 2015 (ML 15239B403), the NRC concluded that Monticello would have moved from Column 3 to Column 4 of the Action Matrix in the 4 th Quarter of 2014, absent a deviation from the Action Matrix which was granted by the NRCs Executive Director for Operations, by letter dated February 27, 2015 (ML15049A132). This deviation resulted in Monticello being placed in the Regulatory Response Column, Column 2 of the Action Matrix.

The placement in Column 2 was due to one or more greater-than-green Security Cornerstone inputs as described in Inspection Report 05000263/2015403 (ML15057A401) issued on February 26, 2015. On June 8, 2015, your staff notified the NRC of your readiness for the NRC to conduct a supplemental inspection to review the actions taken to address the Security Cornerstone performance issues. Beginning on July 20, 2015, the NRC conducted a supplemental inspection in accordance with Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The purpose of the inspection was to provide assurance that: (1) the root causes and contributing causes of risk-significant March 2, 2016 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. Based on the results of that inspection, documented in Inspection Report 05000263/2015407 (ML15245A318), the issue was closed and Monticello returned to the Licensee Response Column as of the 4 th quarter of 2015.

In the February 27, 2015, deviation letter, you agreed to perform an independent safety culture assessment with a focus on human performance. On December 22, 2015, you notified us by letter of your completion of this safety culture assessment. The deviation will remain open until the NRC completes its assessment of your safety culture evaluation. The NRC will inform you by separate correspondence when that assessment will be performed. Should another greater-than-green finding occur while this deviation is open, the NRC will reassess your placement in the Action Matrix consistent with the criteria contained in IMC 0305.

The enclosed inspection plan lists the inspections scheduled through December 31 , 20 17. 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 Monticello, 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 TI 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 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 (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 Darrell Roberts Acting for/

Cynthia D. Pederson Regional Administrator Docket Nos.

50-263 License Nos.

DPR-22 Enclosure:

Inspection Plan cc: Distribution via LISTSERV