IR 05000237/2015005

Mid-Cycle Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2015005; 05000249/2015005)

ML15239B365
Person / Time
Site:	Dresden
Issue date:	09/01/2015
From:	Louden P Division Reactor Projects III
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2015005
Download: ML15239B365 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE , IL 60532-4352 September 1, 2015 Mr. Bryan Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 (REPORT 05000237/2015005; 05000249/2015005

)

Dear Mr. Hanson:

On August 13, 201 5 , the U. S. Nuclear Regulatory Commission (NRC) completed its mid-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 July 1, 20 14 through June 30, 20 15. 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 the performance at Dresden Nuclear Power Station, Unit 2 , during the most recent quarter was within the Regulatory Response Column of the NRC

's Reactor Oversight Process (ROP) Action Matrix due to a PI, "Unplanned Scrams per 7000 Hours," exceeding the Green to White threshold of 3 scrams per 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> in the first quarter of 2015. The PI returned to the Green performance band on April 1, 2015; the required supplemental inspection was completed and documented on August 7, 2015, in NRC Inspection Report 5000237/2015009 (ADAMS Accession Number ML15219A498), at which time Dresden Unit 2 returned to the Licensee Response Column.

Although plant performance is currently assessed in the Licensee Response Column, the NRC has not yet finalized the significance of apparent violation (AV)

050002 37/20100 2-0 4, "Failure to Ensure Continued Operability of Unit 2 Electromatic Relief Valve 2-0203-3 C Following Implementation of Extended Power Uprate Plant Conditions."

The final safety significance determination may affect the NRC's assessment of plant performance and the enclosed inspection plan.

The safety significance of that appare nt violation is anticipated to be finalized in the third quarter of 2015 after you transmit to the NRC your written response to that finding as documented in NRC Inspection Report 05000237/201 5 00 2; 05000249/201 5 00 2, dated August 7 , 2015 (ADAMS Accession Number ML15219A500

). 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 NRC's Reactor Oversight Process (ROP) Action Matrix due to a White violation 05000249/2014005-02, "Failure to Ensure Continued Operability of Unit 3 Electromatic Relief Valve 3-0203-3E Following Implementation of Extended Power Uprate Plant Conditions."

The finding was identified in the fourth quarter of 2014 and documented in NRC Inspection Report 05000237/2014005; 05000249/2014005, dated January 29, 2015 (ADAMS Accession Number ML15029A177).

I n addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 9500 1 , "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," after you notify the NRC of your readiness for that inspection.

The objectives of the supplemental inspection procedure include providing assurance that the root causes and contributing causes of risk-significant performance issues are understood; that the extent of condition and extent of cause of risk-significant performance issues are identified; and that the licensee's corrective actions for risk-significant performance issues are sufficient to address the root and contributing causes and prevent recurrence.

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 second half 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.

The NRC, as shown in the enclosed inspection plan, will conduct a pilot Component Design Baseline Inspection in February 2016 using Inspection Procedure 711121, "Component Design Bases Inspection." Additionally the biennial Problem Identification and Resolution inspection is scheduled for April 2016 using Inspection Procedure 71152, "Problem Identification and Resolution."

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.

The audit has been completed for the first unit at Dresden Nuclear Power Station, and the information gathered will aid staff in development of the ultimate 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 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 Title 10 of the Code of Federal Regulations (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 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 Mr. Jamnes Cameron, DRP , Chief , Branch 4, at 6 30-829-9833 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:

Dresden Nuclear Power Station, Units 2 And 3

Inspection Plan

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