IR 05000443/2014006
| ML14239A182 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/02/2014 |
| From: | Dentel G T Reactor Projects Branch 3 |
| To: | Dean Curtland NextEra Energy Seabrook |
| DENTEL, GT | |
| References | |
| IR-2014-006 | |
| Download: ML14239A182 (5) | |
Text
September 2, 2014
Mr. Dean Curtland Site Vice President Seabrook Nuclear Power Plant NextEra Energy Seabrook, LLC c/o Mr. Michael Ossing P.O. Box 300 Seabrook, NH 03874
SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SEABROOK STATION, UNIT NO. 1 (REPORT 05000443/2014006)
Dear Mr. Curtland:
On August 14, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Seabrook Station, Unit No. 1 (Seabrook). 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, Seabrook was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Seabrook during the most recent quarter was within the Licensee Response Column of the (i.e., green) safety significance, and all performance indicators demonstrated that your performance was within the nominal, expected range (i.e, green). Therefore, the NRC plans to conduct Reactor Oversight Process baseline inspections at your facility. 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 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 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305. The enclosed inspection plan lists the inspections scheduled through December 31, 2015. Routine inspections performed by resident inspectors 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. As part of our baseline inspection program, (ASR) non-conforming condition impacting safety-related reinforced concrete structures at Seabrook. This will be accomplished through scheduled six-month inspection activities using sampling guidance. In addition to baseline inspections, the NRC will perform IP 60855.1, 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-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- Modifying 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 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. 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 me at (610) 337-5233 with any questions you have regarding this letter.
Sincerely,/RA/ Glenn T. Dentel, Chief Projects Branch 3 Division of Reactor Projects Docket No.: 50-443 License No.: NPF-86
Enclosure:
Inspection Plan cc w/encl: Distribution via ListServ
ML14239A182 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME PCataldo/per email MSD MDraxton/ MSD GDentel/ GTD DATE 08/25/14 08/25/14 08/27/14 Distribution w/encl: (via e-mail) W. Dean, RA D. Lew, DRA H. Nieh, DRP M. Scott, DRP J. Trapp, DRS B. Welling, DRS G. Dentel, DRP R. Barkley, DRP M. Draxton, DRP B. Reyes, DRP P. Cataldo, DRP, SRI C. Newport, DRP, RI A. Cass, DRP, Resident 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 RidsNrrPMSeabrook Resource RidsNrrDorlLpl1-2 Resource ROPreports Resource Page 1 of 208/25/201408:58:13Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteSeabrookInspection / Activity Plan07/01/2014-12/31/2015TRI FI-TRIENNIAL FIRE PROTECTION41 IPFire Protection [Triennial]7111105T07/07/201407/11/201471152B-PI&R BIENNIAL21 IPProblem Identification and Resolution71152B10/06/201410/10/20141 IPProblem Identification and Resolution71152B10/20/201410/24/201471124.08-RADWASTE11 IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0808/18/201408/22/2014ASR-PI&R SAMPLE - ASR MONITORING21 IPProblem Identification and Resolution7115210/20/201410/24/2014EP EXER-EP EXERCISE INSPECTION21 IPExercise Evaluation - Hostile Action (HA) Event711140711/03/201411/07/20143-23EXM-INITIAL OL EXAM31 FY15-SEABROOK INITIAL OPERATOR LICENSING EXAMU0191502/17/201503/20/20151 FY15-SEABROOK INITIAL OPERATOR LICENSING EXAMU0191503/23/201504/04/201571151-71151 PI VERIFY IP 71124.01, 02 & 0511 IPRadiological Hazard Assessment and Exposure Controls71124.0112/08/201412/12/20141 IPOccupational ALARA Planning and Controls71124.0212/08/201412/12/20141 IPRadiation Monitoring Instrumentation71124.0512/08/201412/12/20141 IP71151-OR0112/08/201412/12/20141 IP71151-PR0112/08/201412/12/2014ISFSI-ISFSI OPERATIONAL INSPECTION11 IPOperation of an Independent Spent Fuel Storage Installation at Operating Plants60855.103/01/201504/30/2015ASR-PI&R SAMPLE - ASR MONITORING21 IPProblem Identification and Resolution7115203/02/201503/06/2015MODS-PERMANENT PLANT MODIFICATIONS31 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T03/02/201503/06/20151 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T03/16/201503/20/201571124-RAD EFFLUENT CONTROL RETS11 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0604/20/201504/23/20157111107T-TRIENNIAL HEAT SINK11 IPHeat Sink Performance7111107T06/01/201506/05/201571124-REMP11 IPRadiological Environmental Monitoring Program71124.0707/06/201507/09/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
Page 2 of 208/25/201408:58:13Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteSeabrookInspection / Activity Plan07/01/2014-12/31/2015ASR-PI&R SAMPLE - ASR MONITORING21 IPProblem Identification and Resolution7115209/14/201509/18/20157111108P-INSERVICE INSPECTION11 IPInservice Inspection Activities - PWR7111108P10/05/201510/16/20157111111B-REQUAL INSP W/ P/F RESULTS21 IPLicensed Operator Requalification Program7111111B12/07/201512/11/201571124-HP 71124.01 02 03 0411 IPRadiological Hazard Assessment and Exposure Controls71124.0110/19/201510/23/20151 IPOccupational ALARA Planning and Controls71124.0210/19/201510/23/20151 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0310/19/201510/23/20151 IPOccupational Dose Assessment71124.0410/19/201510/23/2015EP-EP PROGRAM INSPECTION11 IPAlert and Notification System Testing711140211/02/201511/06/20151 IPEmergency Preparedness Organization Staffing and Augmentation System711140311/02/201511/06/20151 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140511/02/201511/06/201571151-HP PI VERIFY RAD HAZARD ALARA11 IPRadiological Hazard Assessment and Exposure Controls71124.0112/07/201512/10/20151 IPPerformance Indicator Verification7115112/07/201512/10/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.