IR 05000456/2015006

Annual Assessment Letter for Braidwood Station Units 1 and 2 (Inspection Report 05000456/2015006 and 05000457/2015006)

ML16060A252
Person / Time
Site:	Braidwood
Issue date:	03/02/2016
From:	Jandovitz J S Region 3 Branch 3
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2015006
Download: ML16060A252 (5)

Text

B. Hanson UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I I I 24 43 WARRENVILLE RD

. SUITE 2 1 0 LISLE , I L 60532-4352 Mr. Bryan C. Hanson Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT: ANNUAL ASSESSMENT LETTER FOR BRAIDWOOD STATION UNITS 1 AND 2 (REPORT 05000 456/20 15006 AND 05000 457/20 15006) Dear Mr. Hanson

On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Braidwood Station Units 1 and The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2015 , through December 31, 201 This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facilit The NRC determined that overall, Braidwood Station Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objective The NRC determined the performance Braidwood Station Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRC

's Reactor Oversight Process (ROP) Action 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 enclosed inspection plan lists the inspections scheduled through December 31 , 20 1 Routine inspections performed by resident inspectors are not included in the inspection pla The inspe ctions listed during the last 9 months of the inspection plan are tentative and may be revised at the mid

-cycle performance revie The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issue The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any change This inspection plan does not include security

-related inspections, which will be sent via separate, non

-publicly available correspondenc The NRC inspection schedule includes a biennial inspection conducted in accordance with Inspection Procedure 71152, "Problem Identification and Resolution," and an infrequently performed inspection related to the operation of the Independent Spent Fuel Storage Installation (ISFSI) using IP 60855.1, "Operation of an ISFSI Independent Spent Fuel Storage Installation at Operating Plants."

In response to the accident at Fukushima, the Commission issued Order E A-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for March 2, 2016

B. Hanson -2- Beyond-Design-Basis External Events." This Order 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 even Additionally, the Commission issued Order EA

-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation." This Order 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 even The NRC is conducting audits of licensee efforts towards compliance with these Order The audit was completed for Braidwood Station Units 1 and 2, and the information gathered will aid staff in development of the Safety Evaluation for the sit After the NRC staff receives the Final Compliance letter for the site, the Final Safety Evaluation will be issue Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing TI 191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi

-Unit Dose Assessment Plans."

In accordance with 10 CFR 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 (PARS) component of NRC's document 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 630-829-9763 with any questions you have regarding this lette

Sincerely,

/RA/

John Jandovitz, Acting Chief Branch 3 Division of Reactor Projects Docket Nos. 50

-456; 50-457 License Nos. NPF

-72; NPF-77 Enclosure:

Inspection Plan cc: Distribution via LISTSERV