IR 05000445/2014006

Mid-Cycle Assessment Letter For Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2014006 and 05000446/2014006)

ML14239A248
Person / Time
Site:	Comanche Peak
Issue date:	09/02/2014
From:	Walker W C NRC/RGN-IV/DRP/RPB-A
To:	Flores R Luminant Generation Co
Walker W
References
IR-2014-006
Download: ML14239A248 (6)

Text

September 2, 2014

Rafael Flores, Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Luminant Generation Company LLC Comanche Peak Nuclear Power Plant P.O. Box 1002 Glen Rose, TX 76043

SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 (REPORT 05000445/2014006 AND 05000446/2014006)

Dear Mr. Flores:

On August 12, 2014, the NRC completed its mid-cycle performance review of the Comanche Peak Nuclear Power Plant, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013 through June 30, 2014. This letter informs you of the NRC's assessment of the Comanche Peak Nuclear Power Plant, Units 1 and 2 during this period and its plans for future inspections at your facility. The NRC determined that overall, Comanche Peak Nuclear Power Plant, Units 1 and 2 was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at the Comanche Peak Nuclear Power Plant, Units 1 and 2 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. As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in calendar year 2014 reflect this revision to Inspection Manual Chapter (IMC) 0310. Cross-cutting aspects identified in 2013 using the 2013 terminology were converted to the latest revision in accordance with the cross-reference in IMC 0310 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305. The enclosed inspection plan lists the inspections scheduled through December 31, 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 end-of-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," which 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," which 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 an ultimate 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. 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 me at 817-200-1148 with any questions you have regarding this letter.

Sincerely,/RA/ Wayne C. Walker Chief, Reactor Projects Branch A Division of Reactor Projects Docket Nos.: 50-445; 50-446 License Nos.: NPF-87; NPF-89

Enclosure:

Comanche Peak Nuclear Power Plant, Units 1 and 2 Inspection/Activity Plan