IR 05000387/2015005

ROP-16 Mid-Cycle Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2015005 and 05000388/2015005)

ML15229A102
Person / Time
Site:	Susquehanna
Issue date:	09/01/2015
From:	Scott M L Division Reactor Projects I
To:	Rausch T S Susquehanna
BOWER, FL
References
IR 2015005
Download: ML15229A102 (6)

Text

September 1, 2015

Mr. Timothy President and Chief Nuclear Officer Susquehanna Nuclear, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467

SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (REPORT 05000387/2015005 AND 05000388/2015005)

Dear Mr. Rausch:

On August 11, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Susquehanna Steam Electric Station (Susquehanna) Units 1 and 2. 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 ure inspections at your facility. The NRC determined the performance at Susquehanna Units 1 and 2 during the most recent quarter was within the Regulatory Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of a White finding in the first quarter of 2015 under the Emergency Preparedness Cornerstone. The finding is described in detail in Inspection Report No. 05000387/2015503 and 05000388/2015503 (ADAMS Accession No. ML15105A471). It involved incorrect implementation of the 15-minute assessment, classification, and declaration period for a potential loss of reactor coolant system (RCS) barrier emergency action level. The final significance determination and follow-up assessment were documented in Inspection Report No. 05000387/2015504 and 05000388/2015504 (ML15173A297) issued on June 22, 2015. However, an erratum was issued on June 30, 2015 (ML15181A332), to correctly state that Susquehanna Units 1 and 2 were in the Regulatory Response column of the NRC Action Matrix, retroactive to the first calendar quarter of 2015. In addition to ROP baseline inspections and as a result of the White finding in the Emergency Preparedness Cornerstone, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure Inspection for One or Two White Inputs in a 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 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. In addition to ROP baseline and supplemental Independent Spent Fuel 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-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 onsite portion of the audit was completed at Susquehanna 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 performing Temporary Instruction (TI) 2515/Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi- 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 Fred L. Bower, III at (610) 337-5200 with any questions you have regarding this letter.

Sincerely,/RA/ Michael L. Scott, Director Division of Reactor Projects Docket Nos. 50-387 and 50-388 License Nos. NPF-14 and NPF-22

Enclosure:

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