IR 05000219/2015006

ROP 16 Annual Assessment Letter for Oyster Creek Nuclear Generating Station (Inspection Report 05000219/2015006)

ML16060A019
Person / Time
Site:	Oyster Creek
Issue date:	03/02/2016
From:	Scott M L NRC/RGN-I/DRP/PB6
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
KENNEDY, SR
Shared Package
ML16039A101	List: IR 05000219/2015006 ML16116A278 ML16168A355
References
IR 2015006
Download: ML16060A019 (6)

Text

March 2, 2016

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

SUBJECT: ANNUAL ASSESSMENT LETTER FOR OYSTER CREEK NUCLEAR GENERATING STATION (REPORT 05000219/2015006)

Dear Mr. Hanson:

On February 9, 2016, the U. S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Oyster Creek Nuclear Generating Station. 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 your facility. The NRC determined that overall, Oyster Creek Nuclear Generating Station operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Oyster Creek Nuclear Generating Station 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. In accordance with Inspection MOperating Reactor Assessment Oyster Creek Nuclear Generating Station transitioned from the Regulatory Response Column to the Licensee Response Column of the ROP Action Matrix on November 5, 2015, following the successful completion of two supplemental inspections. Inspection Procedure (IP) Supplemental Inspection for One or Two White Inputs in a Strategic Performance Areawas completed on September 4, 2015, to address a White finding in the Mitigating Systems cornerstone associated with an inadequate review of a change in a maintenance process that resulted in an inoperable emergency diesel generator (ADAMS Accession Number ML15288A480). A second IP 95001 inspection was completed on September 25, 2015, to Scrams Per 7 (ML15351A416) and closed out one Yellow finding associated with the inadequate application of materials, parts, equipment, and procedures associated with electromagnetic relief valves. Because the finding was considered an old design issue in accordance with Inspection Manual Chapter 0305, it was not an input in the assessment process or an NRC Action Matrix Input. 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. In addition to baseline inspections, the NRC will perform Inspection Procedure (IP) 60855.1, Operation of an ISFSI Independent Spent Fuel Storage Installation at Operating Plants 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-Bguidance 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-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. 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 the Final 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. Following the audit, and 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 2515-191Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communications/ Staffing/Multi-Unit Dose Assessment Plans. As noted in the enclosure, this inspection has been scheduled for Oyster Creek Nuclear Generating Station. During the assessment period, the NRC issued two Severity Level IV traditional enforcement violations to Oyster Creek Nuclear Generating Station. One traditional enforcement violation involved incomplete Title 10 of the Code of Federal Regulations (10 CFR) 50.72 and 50.73 reports associated with secondary containment integrity. The second traditional enforcement violation involved the use of an analytical method to determine core operating limits without prior NRC approval. In accordance with NRC Inspection Manual Chapter 0305, Section 13.02.b, the NRC will follow up on the first violation through a baseline inspection and the second through -up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, and Alternative In accordance with Title 10 of the Code of Federal Regulations (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 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