IR 05000456/2011006
| ML112440151 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/01/2011 |
| From: | Eric Duncan Region 3 Branch 3 |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-11-006 | |
| Download: ML112440151 (7) | |
Text
September 1, 2011
SUBJECT:
MID-CYCLE LETTER FOR BRAIDWOOD STATION, UNITS 1 AND 2; 05000456/2011-006; 05000457/2011-006
Dear Mr. Pacilio:
On August 9, 2011, the Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Braidwood Station, 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, 2010, through June 30, 2011. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRCs assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined the performance at Braidwood Station Unit 1 during the most recent quarter was within the Licensee Response Column of the NRCs 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). Performance at Braidwood Station Unit 1 was within the Regulatory Response Column of the ROP Action Matrix during the first two quarters of this assessment period due to a White finding that involved the June 24, 2009, failure of the Unit 1 Containment Sump Suction Isolation Valve 1SI8811B to open during surveillance testing. This finding was closed on November 26, 2010, as documented in our Assessment Follow-Up letter to you dated December 2, 2010 [ML103360350]. Unit 1 returned to the Licensee Response Column in the first quarter of 2011.
The NRC determined the performance at Braidwood Station Unit 2 during the most recent quarter, as well as the first three quarters of the assessment period, was within the Licensee Response Column of the NRCs 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 Braidwood Station. From July 1, 2010, to June 30, 2011, the NRC issued four Severity Level IV traditional enforcement violations to Braidwood Station. Three of these Severity Level IV violations involved examples in which the regulatory process was impeded. Therefore, the NRC plans to conduct inspection activities using Inspection Procedure (IP) 92723, Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12-Month Period, to follow-up on these violations. The remaining Severity Level IV violation was associated with a compliance backfit issue. Consistent with the NRCs practice in reviewing compliance backfit issues, the NRC will perform IP 92723 at your facility to review your efforts to implement corrective actions and identify any extent of condition concerns associated with the compliance backfit issue.
The enclosed inspection plan lists the inspections scheduled through December 31, 2012.
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. 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. The NRC also plans to conduct several special and infrequently performed inspections, which include inspections related to the pre-operational testing and operation of the Independent Spent Fuel Storage Installation.
In the days following the Fukushima Daiichi nuclear accident in Japan, the Commission directed the staff to establish a senior-level agency task force to conduct a methodical and systematic review of the NRCs processes and regulations to determine whether the agency should make additional improvements to its regulatory system. The NRC has since completed Temporary Instruction (TI) 183, Follow-up to Fukushima Daiichi Nuclear Station Fuel Damage Event, and TI-184, Availability and Readiness Inspection of Severe Accident Management Guidelines (SAMGs) at your facility. Results of these inspections can be found here:
http://www.nrc.gov/japan/japan-activities.html. Additionally, on May 11, 2011, the agency issued NRC Bulletin 2011-01, Mitigating Strategies, to confirm compliance with Order EA-02-026, subsequently imposed license conditions, and 10 CFR 50.54(hh)(2), and to determine the status of licensee mitigating strategies programs. On July 12, 2011, the NRCs Task Force made its recommendations to the Commission in its report, Recommendations for Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident. The NRC is currently reviewing the Task Forces recommendations to determine what additional actions may be warranted.
In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter and its enclosure will be made 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 630-829-9620 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Eric R. Duncan, Chief Branch 3 Division of Reactor Projects
Docket Nos. 50-456, 50-457 License Nos. NPF-72, NPF-77
Enclosure: Braidwood Station Inspection/Activity Plan
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