IR 05000237/2015006

Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Inspection Report 05000237/2015006 and 05000249/2015006)

ML16060A272
Person / Time
Site:	Dresden
Issue date:	03/02/2016
From:	Louden P Division Reactor Projects III
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2015006
Download: ML16060A272 (6)

Text

UNITED STATES rch 2, 2016

SUBJECT:

ANNUAL ASSESSMENT LETTER FOR DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 (REPORT 05000237/2015006 AND 05000249/2015006)

Dear Mr. Hanson:

On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Dresden Nuclear Power Station, Units 2 and 3. 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 the performance at Dresden Nuclear Power Station, Unit 2, during the most recent quarter was within the Regulatory Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of issues identified with the units C electromatic relief valves (ERV) ability to perform its intended safety function as described in Inspection Report 05000237/2015010 (ML15260A508) dated September 16, 2015. A supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, was successfully performed and documented in Inspection Report 05000237/2015011; 05000249/2015011, (ML15336A721) dated December 2, 2015. That inspection report stated that Dresden Nuclear Power Station, Unit 2, would remain in Regulatory Response Column until the end of the first quarter of 2016 assuming no additional greater-than-green findings; Dresden Nuclear Power Station, Unit 2, entered the Regulatory Response Column in the second quarter of 2015 due to the ERV issue.

The NRC determined the performance at Dresden Nuclear Power Station, Unit 3, during the most recent quarter was within the Regulatory Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of issues identified with the units E valve ERVs ability to perform its intended safety function as described in Inspection Report 05000249/2015008 (ML15085A273), dated on March 26, 2015. A supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, was successfully performed and documented in Inspection Report 05000237/2015011; 05000249/2015011 (ML15336A721) dated December 2, 2015. That inspection report stated that Dresden Nuclear Power Station, Unit 3, would remain in Regulatory Response Column until the issuance of the report; Dresden Nuclear Power Station, Unit, transitioned to the Licensee Response Column on December 2, 2015. 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 biennial inspection conducted in accordance with Inspection Procedure 71152, Problem Identification and Resolution, a triennial inspection conducted in accordance with Inspection Procedure 7111121, Component Design Bases Inspection, and an infrequently performed inspection related to the operation of the Independent Spent Fuel Storage Installation (ISFSI) using IP 60855.1, Operation of an ISFSI Independent Spent Fuel Storage Installation at Operating Plants.

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 Dresden Nuclear Power Station, Units 2 and 3, 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 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 Mr. Jamnes Cameron at 630-829-9833 with any questions you have regarding this letter.

Sincerely,

/RA/

Patrick L. Louden, Director Division of Reactor Projects Docket Nos. 50-237; 50-249 License Nos. DPR-19; DPR-25 Enclosure:

Inspection Plan cc: Distribution via LISTSERV