IR 05000272/2015005

ROP-16 Mid-Cycle Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Report 05000272/2015005 and 05000311/2015005)

ML15229A044
Person / Time
Site:	Salem
Issue date:	09/01/2015
From:	Scott M L Division Reactor Projects I
To:	Braun R Public Service Enterprise Group
DENTEL, GT
References
IR 2015005
Download: ML15229A044 (8)

Text

September 1, 2015

Mr. Robert Braun President and Chief Nuclear Officer PSEG Nuclear LLC N09 P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 (REPORT 05000272/2015005 AND 05000311/2015005)

Dear Mr. Braun:

On August 12, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem). 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 r future inspections at your facility. The NRC determined the performance at Salem Unit 2 during the most recent quarter was 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. The NRC determined the performance at Salem Unit 1 during the most recent quarter was within the Regulatory Response Column of the NRCs ROP Action Matrix because in the fourth Unplanned Scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> criticalthreshold, which moved Salem Unit 1 to the Regulatory Response Column from the Licensee Response Column. You were notified of this change to the ROP Action Matrix Column in the NRC Annual Assessment Letter 05000272/2014001, issued March 4, 2015 (ADAMS Accession No. ML15062A086). Although the above described PI returned to the nominal, expected range (i.e., green) in the second quarter of 2015, completion of the required supplemental inspection in accordance with Inspection Procedure (IP) 95001 Two is required to return Salem Unit 1 to the Licensee Response Column. On May 29, 2015, your staff notified the NRC of your readiness to conduct a supplemental inspection to review the actions taken to address the White PI described above. In response, the NRC conducted a supplemental inspection in accordance with IP 95001 during the week of July 20, 2015. The objectives of the IP 95001 inspection were to provide assurance that the root cause and contributing causes of risk significant performance issues were understood, the extent of condition and extent of cause were understood, and the corrective actions were sufficient to address the root and contributing causes and prevent recurrence. As of the date of this letter, the IP 95001 inspection report and assessment follow up letter have not been issued. The NRC will notify you of the results of this inspection via a separate inspection report which will be publically available. 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. The inspections listed during the second half 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 addition to baseline inspections, the NRC will conduct Inspection Procedure (IP) 60855.1, -the license conditions added as part of the renewed operating license, regulatory commitments, selected aging management programs (AMPs), and time limited aging analyses (TLAAs) are implemented and/or completed in accordance with 10 CFR Part 54. As discussed below, the NRC will also perform Temporary Instruction (TI) 2515-Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans 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-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-o 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. The on-site portion of the audit has been completed at Salem Units 1 and 2, and the information gathered will aid staff in development of the Final Safety Evaluation for the site. 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 2515-191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans. From July 1, 2014 through June 30, 2015, the NRC issued two Severity Level IV traditional enforcement violations associated with impeding the regulatory process (one) and deliberate misconduct (one). Therefore, the NRC plans to conduct Inspection Procedure -up on Correcti-up on these violations. 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 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 Glenn Dentel at (610) 337-5233 with any questions you have regarding this letter.

Sincerely,/RA/ Michael L. Scott, Director Division of Reactor Projects Docket Nos. 50-272, 50 311 License Nos. DPR 70, DPR 75

Enclosure:

Salem Inspection/Activity Plan cc w/encl: Distribution via ListServ