IR 05000219/2015005

ROP-16 Mid-Cycle Assessment Letter for Oyster Creek Nuclear Generating Station (Report 05000219/2015005)

ML15229A114
Person / Time
Site:	Oyster Creek
Issue date:	09/01/2015
From:	Scott M L Division Reactor Projects I
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
KENNEDY, SR
References
IR-2015005
Download: ML15229A114 (6)

Text

September 1, 2015

Mr. Bryan Hanson Senior Vice President, Exelon Generation President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR OYSTER CREEK NUCLEAR GENERATING STATION (REPORT 05000219/2015005)

Dear Mr. Hanson:

On August 13, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Oyster Creek Nuclear Generating Station (Oyster Creek). The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2014, through June 30, 2015. This letter informs you of your facility, and its plans for future inspections at your facility. The NRC determined that performance at Oyster Creek during the most recent quarter was within the Regulatory Response Matrix because one finding of White significance, associated with the Mitigating Systems cornerstone, was identified in the fourth quarter 2014 integrated inspection report (ADAMS Accession No. ML15042A072). The finding was associated with an inadequate review of a change in maintenance process that caused an inoperable emergency diesel generator (EDG). The final significance determination and follow-up assessment letter for this finding issued on April 27, 2015, documented that Oyster Creek transitioned to the Regulatory Response Column of the ROP Action Matrix in accordance with Inspection Manual Chapter (IMC) 0305, retroactive to the fourth quarter of 2014. On July 14, 2015, your staff notified the NRC of your readiness for a supplemental inspection to review the actions taken to address the White finding described above. In response, the NRC will conduct a supplemental inspection in accordance with Inspection for One or Two White Inputs in a Strategic Performance Areaduring the week of August 31, 2015. The objectives of the 95001 inspection are to provide assurance that the root cause and contributing causes of risk-significant performance issues are understood, the extent of condition and extent of cause are understood, and the corrective actions are sufficient to address the root and contributing causes and prevent recurrence. The NRC will notify you of the results of this inspection via a separate inspection report which will be publically available. -to-White threshold, based on PI data submitted in July 2015. Specifically, this PI crossed the Green-to-White threshold due to unplanned scrams on July 11, 2014; October 12, 2014; March 22, 2015; and May 7, 2015. Because the White PI was not in the same Cornerstone as the White finding related to the EDG, discussed above, Oyster Creek will remain in the Regulatory Response Column of the ROP Action Matrix. On August 18, , your staff notified the NRC of your readiness for a supplemental inspection to review the actions taken to address the White PI. The NRC will conduct a supplemental inspection using The objectives of the 95001 supplemental inspection were discussed above. On April 27, 2015, the NRC issued the final significance determination and follow-up assessment letter (ML15112A147) for a Yellow finding associated with the inadequate application of materials, parts, equipment and processes associated with electromatic relief valves. The letter stated that, because the finding was considered an old design issue in accordance with IMC 0305, it will not be used as input in the assessment process or NRC Action Matrix. However, in accordance with IMC 0305, the NRC will conduct a supplemental for One Degraded notify us of their readiness for this inspection. The objectives of this 95002 inspection are to provide assurance that root and contributing causes of risk-significant performance issues are understood, to independently assess and provide assurance that the extent of condition and the extent of cause are identified, and to provide assurance that corrective actions are sufficient to address the root and contributing causes and prevent recurrence. The enclosed inspection plan lists the inspections scheduled through June 30, 2017. Routine inspections performed by resident inspectors are not included in the inspection plan. In addition Independent Spent Fuel Storage Installation at Operating Plants, and Temporary Instruction (TI) 2515-191Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communications/Staffing/Multi-Unit Dose Assessment Plans. 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-Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-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-g Licenses with Regard to Reliable Spent Fuel Pool 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 has been scheduled for the week of May 2, 2016. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. From July 1, 2014, through June 30, 2015, the NRC issued two severity level (SL) IV traditional enforcement violations associated with impeding the regulatory process. The NRC plans to follow-up on these violations by conducting Inspection Procedure 92702, or standard baseline inspection procedures, as described in IMC 0305, Section 13.02.b. In accordance with Title 10 of the Code of Federal Regulationse electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the 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 Silas Kennedy at (610) 337-5046 with any questions you have regarding this letter.

Sincerely,/RA/ Michael L. Scott, Director Division of Reactor Projects Docket Nos. 50-219 License Nos. DPR-16

Enclosure:

Oyster Creek Nuclear Generating Station Inspection/Activity Plan cc w/encl: Distribution via ListServ