IR 05000219/2014006
| ML14239A222 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/02/2014 |
| From: | Ho Nieh Division Reactor Projects I |
| To: | Pacilio M J Exelon Generation Co, Exelon Nuclear |
| Kennedy, SR | |
| References | |
| IR-2014-006 | |
| Download: ML14239A222 (6) | |
Text
[Addressee, First September 2, 2014 Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Rd. Warrenville, IL 60555
SUBJECT: MID-CYCLE ASSESSMENT AND ASSESSMENT FOLLOW-UP LETTER FOR OYSTER CREEK NUCLEAR GENERATING STATION (REPORT 05000219/2014006)
Dear Mr. Pacilio:
On August 12, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Oyster Creek Nuclear Generating Station. The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from July 1, assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Oyster Creek Nuclear Generating Station was 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 Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all performance indicators indicated that your performance was within the nominal, expected range (i.e, green). Although plant performance was within the Licensee Response Column throughout the previous four quarters, as a result of its continuous review of plant performance, the NRC identified that crossed the Green-to-White threshold with the unplanned scram on July 11, 2014. Specifically, Oyster Creek Nuclear Generating Station crossed the Green-to-White threshold following unplanned scrams on October 3, October 6, and December 14, 2013, and July 11, 2014. Although the Action Matrix column designation for the Oyster Creek Nuclear Generating Station will not change until the PI data are submitted, reviewed and posted following the end of the third calendar quarter, planning and scheduling activities in anticipation of an Inspection Procedure 95001, occur. The NRC will be in contact to discuss when your staff will be ready for this inspection. This inspection is conducted to provide assurance that the root cause and contributing causes of risk significant performance issues are understood, the extent of condition is identified, and the corrective actions are sufficient to prevent recurrence. The enclosed inspection plan lists the inspections scheduled through December 31, 2015. Routine inspections performed by resident inspectors, as well as the IP 95001 which will result from the White performance indicator at the end of the third calendar quarter, are not included in the inspection plan. 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-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-t 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 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. As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in calendar year 2014 will reflect this revision to Inspection Manual Chapter (IMC) 0310. Cross-cutting aspects identified in 2013 using the 2013 terminology were converted to the latest revision in accordance with the cross-reference in IMC 0310, and were evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305. In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390 of the inspection in the NRC Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Document 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/ Ho K. Nieh Director Division of Reactor Projects Docket Nos.: 50-219 License Nos.: DPR-16
Enclosure:
Inspection Plan cc w/encl: Distribution via ListServ
ML14239A222 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP RI/DRP NAME JKulp/ LC for LCline/ LC SKennedy/SRK HNieh/ HKN DATE 08/21/14 08/26/14 08/27/14 08 /28 /14 Distribution w/encl: W. Dean, RA D. Lew, DRA H. Nieh, DRP M. Scott, DRP J. Trapp, DRS B. Welling, DRS S. Kennedy, DRP L. Cline, Acting, DRP C. Roettgen, DRP B. Bollinger, DRP J. Kulp, DRP, SRI Amar Patel, DRP, RI J. DeVries, DRP, AA A. Bowers, RI OEDO R. J. Powell, DRP DRS Branch Chiefs (6) N. McNamara, RI, SLO D. Tifft, RI, SLO D. Screnci, RI, PAO N. Sheehan, RI, PAO RidsNrrDirslpab Resource ROPassessment Resource RidsNrrPMOysterCreek Resource RidsNrrDorlLpl1-2 Resource ROPReports Resource Page 1 of 208/26/201409:34:44Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteOyster CreekInspection / Activity Plan07/01/2014-12/31/201571124-HP INSPECTION RAD HAZARD ALARA11 IPRadiological Hazard Assessment and Exposure Controls71124.0108/11/201408/14/20141 IPOccupational ALARA Planning and Controls71124.0208/11/201408/14/20147111108G-INSERVICE INSPECTION11 IPInservice Inspection Activities - BWR7111108G09/22/201409/26/201471124-HP INSPECTION IP 71124.01 .02 .03 0411 IPRadiological Hazard Assessment and Exposure Controls71124.0109/22/201409/26/20141 IPOccupational ALARA Planning and Controls71124.0209/22/201409/26/20141 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0309/22/201409/26/20141 IPOccupational Dose Assessment71124.0409/22/201409/26/2014EP PROG-EP PROGRAM INSPECTION11 IPAlert and Notification System Testing711140209/22/201409/26/20141 IPEmergency Preparedness Organization Staffing and Augmentation System711140309/22/201409/26/20141 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140509/22/201409/26/201471152B-PI&R BIENNIAL51 IPProblem Identification and Resolution71152B11/03/201411/07/20141 IPProblem Identification and Resolution71152B11/17/201411/21/201471152-PIR SAMPLE - EDG DEGRADED WRIST PIN11 IPProblem Identification and Resolution7115210/06/201410/10/201471124-71124.05 RAD MONITORING INSTRUMENTATION11 IPRadiation Monitoring Instrumentation71124.0510/20/201410/24/201471151-71151 PI VERIFY 71124.01.02.03.04 SAMPLE11 IPRadiological Hazard Assessment and Exposure Controls71124.0111/17/201411/21/20141 IPOccupational ALARA Planning and Controls71124.0211/17/201411/21/20141 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0311/17/201411/21/20141 IPOccupational Dose Assessment71124.0411/17/201411/21/20141 IP71151-OR0111/17/201411/21/20141 IP71151-PR0111/17/201411/21/201471124-HP INSPECTION 71124.01 AND .0211 IPRadiological Hazard Assessment and Exposure Controls71124.0101/26/201501/30/20151 IPOccupational ALARA Planning and Controls71124.0201/26/201501/30/20157111107T-TRIENNIAL HEAT SINK11 IPHeat Sink Performance7111107T03/09/201503/13/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
Page 2 of 208/26/201409:34:44Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteOyster CreekInspection / Activity Plan07/01/2014-12/31/2015MODS-PERMANENT PLANT MODIFICATIONS31 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T04/06/201504/10/20151 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T04/20/201504/24/201571124-RADIOACTIVE EFFLUENT CONTROL RETS11 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0605/25/201505/28/20157111111B-REQUAL INSP W/ P/F RESULTS21 IPLicensed Operator Requalification Program7111111B06/08/201506/12/201571124-REMP11 IPRadiological Environmental Monitoring Program71124.0708/03/201508/06/2015EP-EP EXERCISE61 IPExercise Evaluation - Hostile Action (HA) Event711140709/28/201510/02/20151 IPExercise Evaluation - Scenario Review711140809/28/201510/02/201571151-RP CHEM PI VERIFY RAD HAZARD11 IPRadiological Hazard Assessment and Exposure Controls71124.0111/02/201511/05/20151 IPPerformance Indicator Verification7115111/02/201511/05/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.