IR 05000333/2014006

Mid-Cycle Assessment Letter and Inspection Plan 2014 (ROP-15) - James A. FitzPatrick Nuclear Power Plant (Report 05000333/2014006)

ML14241A040
Person / Time
Site:	FitzPatrick
Issue date:	09/02/2014
From:	Ho Nieh Division Reactor Projects I
To:	Coyle L Entergy Nuclear Northeast
Burritt A L
References
IR-2014-006
Download: ML14241A040 (6)

Text

September 2, 2014

Mr. Lawrence Coyle Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P. O. Box 110 Lycoming, NY 13093

SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (REPORT 05000333/2014006)

Dear Mr. Coyle:

On August 13, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from July 1, 2013 through June 30, 2014. 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 that overall, FitzPatrick was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at FitzPatrick during the most recent quarter was within the Regulatory Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix, because all inspection findings had very low safety significance (Green) and one performance indicator was of low to moderate safety significance (White) in the Initiating Events cornerstone. Specifically, the "Unplanned Power Changes per 7,000 Critical Hours" performance indicator exceeded the Green/White threshold value in the fourth quarter of 2012. From January 20 through 24, 2014, NRC inspectors conducted the onsite portion of a supplemental inspection for the White performance indicator in accordance with Inspection Procedure (IP) 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The NRC inspectors concluded that the corrective actions taken by FitzPatrick to preclude repetition of the unplanned power changes were not sufficient to meet the inspection objectives. As a result, the inspection was not closed and remains open until additional corrective actions, including the replacement of the condenser tubes during the current refueling outage, have been completed. The NRC will review Entergy's implementation of these additional corrective actions during a future inspection. The performance indicator will continue to be a White ROP Action Matrix input until the performance indicator results allow it to transition below the Green/White threshold. The NRC will notify you via separate correspondence when the plant will transition to the Licensee Response Column.

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. In addition to baseline inspections, the NRC will perform IP 71003, "Post-Approval Site Inspection for License Renewal," and IP 60855, "Operation of an Independent Spent Fuel Storage Installation (ISFSI)." 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-12-049, "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. 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 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 component of the NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Please contact Arthur Burritt at (610)337-5069 with any questions you have regarding this letter.

Sincerely,/RA/ Ho K. Nieh Director Division of Reactor Projects Docket No. 50-333 License No. DPR-59

Enclosure:

Inspection Plan

cc w/encl: Distribution via ListServ

ML14241A040 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME TSetzer/TCS ABurritt/ALB HNieh/HKN DATE 08/20/14 08/25/14 08/28/14 Page 1 of 208/19/201410:32:08Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteFitzPatrickInspection / Activity Plan07/01/2014-12/31/20159/22EXAM-INITIAL OL EXAM (2)41 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)U0188808/18/201408/22/20141 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)U0188809/22/201410/02/2014EP PROG-EP PROGRAM INSPECTION11 IPAlert and Notification System Testing711140207/07/201407/11/20141 IPEmergency Preparedness Organization Staffing and Augmentation System711140307/07/201407/11/20141 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140507/07/201407/11/201471124-RADIATION SAFETY INSPECTION11 IPRadiation Monitoring Instrumentation71124.0507/14/201407/18/201471003-LR COMMITMENTS INSP PHASE 231 IPPost-Approval Site Inspection for License Renewal7100308/11/201408/15/20141 IPPost-Approval Site Inspection for License Renewal7100308/25/201408/29/20147111108G-INSERVICE INSPECTION11 IPInservice Inspection Activities - BWR7111108G09/03/201409/10/201471124-RADIATION SAFETY11 IPRadiological Hazard Assessment and Exposure Controls71124.0109/01/201409/05/20141 IPOccupational ALARA Planning and Controls71124.0209/01/201409/05/20141 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0309/01/201409/05/20141 IPOccupational Dose Assessment71124.0409/01/201409/05/20141 IPPerformance Indicator Verification7115109/01/201409/05/201471124-RAD SAFETY INSP11 IPRadiological Hazard Assessment and Exposure Controls71124.0111/17/201411/21/20141 IPOccupational ALARA Planning and Controls71124.0211/17/201411/21/20141 IPRadiation Monitoring Instrumentation71124.0511/17/201411/21/2014TRI FI-TRIENNIAL FIRE PROTECTION51 IPFire Protection [Triennial]7111105T12/01/201412/05/20141 IPFire Protection [Triennial]7111105T12/15/201412/19/2014ISFSI-ISFSI OPERATIONAL INSPECTION11 IPOperation Of An ISFSI6085503/01/201504/30/20151 IPOperation of an Independent Spent Fuel Storage Installation at Operating Plants60855.103/01/201504/30/20158/3EXAM-INITIAL OL EXAM41 FY15-FITZ INITIAL OPERATOR LICENSING EXAMU0190707/06/201508/10/20151 FY15-FITZ INITIAL OPERATOR LICENSING EXAMU0190708/03/201508/07/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.

Page 2 of 208/19/201410:32:08Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteFitzPatrickInspection / Activity Plan07/01/2014-12/31/201571124-RAD SAFETY INSPECTION11 IPRadiological Hazard Assessment and Exposure Controls71124.0104/06/201504/10/20151 IPOccupational ALARA Planning and Controls71124.0204/06/201504/10/20151 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0304/06/201504/10/20151 IPOccupational Dose Assessment71124.0404/06/201504/10/20151 IPPerformance Indicator Verification7115104/06/201504/10/2015MODS-PERMANENT PLANT MODIFICATIONS31 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T06/01/201506/05/20157111107T-TRIENNIAL HEAT SINK11 IPHeat Sink Performance7111107T06/08/201506/12/2015MODS-PERMANENT PLANT MODIFICATIONS31 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T06/15/201506/19/201571124.07-RAD SAFETY INSPECTION11 IPRadiological Environmental Monitoring Program71124.0707/20/201507/24/20151 IPPerformance Indicator Verification7115107/20/201507/24/201571124-RAD SAFETY INSPECTION11 IPRadiological Hazard Assessment and Exposure Controls71124.0109/14/201509/18/20151 IPOccupational ALARA Planning and Controls71124.0209/14/201509/18/20151 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0309/14/201509/18/20151 IPOccupational Dose Assessment71124.0409/14/201509/18/2015EP-EP EXERCISE51 IPExercise Evaluation - Hostile Action (HA) Event711140710/19/201510/23/20151 IPExercise Evaluation - Scenario Review711140810/19/201510/23/201571124-RAD SAFETY INSP11 IPRadiological Hazard Assessment and Exposure Controls71124.0111/16/201511/20/20151 IPOccupational ALARA Planning and Controls71124.0211/16/201511/20/20151 IPRadiation Monitoring Instrumentation71124.0511/16/201511/20/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.