IR 05000285/2015006

Annual Assessment Letter for Fort Calhoun Station (Report 05000285/2015006)

ML16061A344
Person / Time
Site:	Fort Calhoun
Issue date:	03/02/2016
From:	Pruett T W NRC/RGN-IV/DRP
To:	Marik S Omaha Public Power District
Miller G B
References
IR 2015006
Download: ML16061A344 (6)

Text

SUBJECT: ANNUAL ASSESSMENT LETTER FOR FORT CALHOUN STATION (REPORT 05000285/2015006)

Dear Mr. Marik:

On February 17, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Fort Calhoun Station. 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, Fort Calhoun Station operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Fort Calhoun Station during the most recent quarter was within the Licensee Response Column (Column 1) 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.

During this end-of-cycle performance review, the NRC identified a cross-cutting theme in the Human Performance area, with 21 findings with cross-cutting aspects in that area. Because the NRC also identified this same theme in its previous mid-cycle performance review (ML15243A581), this is the second consecutive assessment meeting with the same cross-cutting theme. In accordance with NRC Inspection Manual Chapter 0305, "Operating Reactor Assessment Program," section 14.02, the NRC considered the effectiveness of your actions and decided not to perform additional follow-up of those actions at this time. The improvement plan the station has implemented, as well as the improving trend in cross-cutting aspects over the past six months were the basis for this decision. The NRC will continue to monitor this theme. 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 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. 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, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans." 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. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of a Safety Evaluation for the site. The date for the onsite component at your site is being coordinated with your staff. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. Following the audit, and 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 Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," 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 Geoff Miller at 817-200-1173 with any questions you have regarding this letter.

Sincerely,/RA/ Troy W. Pruett, Director Division of Reactor Projects Docket No. 50-285 License No. DPR-40

Enclosure:

Fort Calhoun Inspection/Activity Plan