IR 05000373/2015006
| ML16060A284 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/02/2016 |
| From: | Billy Dickson NRC/RGN-III/DRP/B5 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2015006 | |
| Download: ML16060A284 (6) | |
Text
SUBJECT:
ANNUAL ASSESSMENT LETTER FOR LASALLE COUNTY STATION, UNITS 1 AND 2 (REPORT 05000373/2015006 AND 05000374/2015006)
Dear Mr. Hanson:
On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of LaSalle County Station, 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, 2015, through December 31, 2015. 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, LaSalle County Station, 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 LaSalle County Station, 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 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.
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 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.
The NRC inspection schedule includes a triennial inspection conducted in accordance with Inspection Procedure 71111.21, Component Design Bases Inspection and an infrequently performed inspection related to follow-up on previously documented deviations using Inspection Procedure 92702, Follow-up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, and Alternative Dispute Resolution Confirmatory Orders. In addition, from January 1 to December 31, 2015, the NRC issued four Severity Level IV traditional enforcement violations associated with impeding the March 2, 2016 regulatory process. Therefore, the NRC had conducted Inspection Procedure 92723, Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12-Month Period, to follow-up on these violations in February 2016. The results of this inspection will be provided to you in an integrated inspection report to be issued later.
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 LaSalle County Station, Units 1 and 2, and the information gathered will aid staff in development of a 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 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 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 630-829-9827 with any questions you have regarding this letter.
Sincerely,
/RA/
Billy Dickson, Chief Branch 5 Division of Reactor Projects
Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18
Enclosure:
Inspection Plan
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