IR 05000313/2013001
| ML14063A150 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/04/2014 |
| From: | Greg Werner NRC/RGN-IV/DRP/RPB-E |
| To: | Jeremy G. Browning Entergy Operations |
| Werner G | |
| References | |
| IR-13-001 | |
| Download: ML14063A150 (5) | |
Text
March 4, 2014
SUBJECT:
ANNUAL ASSESSMENT LETTER FOR ARKANSAS NUCLEAR ONE UNITS 1 AND 2 (REPORT 05000313/2013001 AND 05000368/2013001)
Dear Mr. Browning:
On February 13, 2014, the NRC completed its end-of-cycle performance review of the Arkansas Nuclear One, 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, 2013, through December 31, 2013. 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, Arkansas Nuclear One, Units 1 and 2, operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at the Arkansas Nuclear One, Units 1 and 2, 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.
Although plant performance was within the Licensee Response Column, the NRC is still evaluating potential greater than green issues related to unresolved items identified in Augmented Inspection Team report 05000313/2013011; 05000368/2013011 following the Unit 1 stator drop event. These issues will be documented in the Augmented Inspection Team Follow-up report 05000313/2013012; 05000368/2013012. The final safety significance determination associated with any findings may affect the NRCs assessment of plant performance and the enclosed inspection plan.
The enclosed inspection plan lists the inspections scheduled through June 30, 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 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. 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, is ongoing. This audit includes an onsite component in order for the NRC to evaluate mitigating strategies as described in licensee 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.
As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised effective January 1, 2014. New cross-cutting aspects will be coded in accordance with the latest revision to NRC Inspection Manual Chapter (IMC) 0310, dated December 19, 2013. Cross-cutting aspects identified in the last six months of 2013 using the previous terminology will be converted to the revised language in accordance with the cross-reference in IMC 0310. The revised cross-cutting aspects will be evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305 starting with the calendar year 2014 mid-cycle assessment.
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 me at 817-200-1574 with any questions you have regarding this letter.
Sincerely,
/RA/
Gregory E. Werner, Acting Chief Project Branch E Division of Reactor Projects
Docket Nos.: 50-313, 50-368 License Nos: DRP-51; NPF-6
Enclosure:
Inspection Plan