IR 05000454/2008001

Byron, EOC Annual Assessment Letter (Report 05000454-08-001 and 05000455-08-001)

ML080600260
Person / Time
Site:	Byron
Issue date:	03/03/2008
From:	Pederson C Division Reactor Projects III
To:	Pardee C Exelon Generation Co
References
IR-08-001
Download: ML080600260 (7)

Text

rch 3, 2008

SUBJECT:

ANNUAL ASSESSMENT LETTER - BYRON STATION, UNITS 1 AND 2 05000454/2008001 AND 05000455/2008001

Dear Mr. Pardee:

On February 13, 2008, the NRC staff completed its performance review of Byron Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2007. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.

This performance review and enclosed inspection plan do not include security information. A separate letter designated and marked as "Official Use Only - Security Related Information" will include the security cornerstone review and resultant inspection plan.

Overall, Byron Station, Units 1 and 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Unit 1 performance for the most recent quarter was within the Licensee Response column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight process (ROP) baseline inspections at your facility. Although Unit 1 performance was within the Licensee Response column, the significance of the degradation of the Essential Service Water (SX) risers is still under review as part of the Significance Determination Process which, when finalized, may change our assessment of your plants safety performance.

Unit 2 performance for the most recent quarter was within the Regulatory Response column of the NRCs Action Matrix, based on a White Mitigating System Performance Index, Heat Removal Systems PI originating in the second quarter of CY 2006. Although Unit 2 performance was within the Regulatory Response column, the degradation of the Essential Service Water (SX) risers is still under review as part of the Significance Determination Process which, when finalized, may change our assessment of your plants safety performance. On January 10, 2007, we were notified by your staff of your readiness for the NRC to conduct a supplemental inspection to review the actions taken to address the White Mitigating System Performance Index, Heat Removal Systems performance indicator. We conducted supplemental inspection procedure 95001 during the week of February 5, 2007. Based on the results of this inspection, no findings of significance were identified. Therefore, pending the outcome of the significance determination of the SX riser issue, we plan to conduct reactor oversight process (ROP) baseline inspections at your facility.

The enclosed inspection plan details the inspections, including baseline and other infrequently conducted inspections, less those related to security, scheduled through June 30, 2009. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last nine months of the inspection plan are tentative and may be revised at the mid-cycle review.

In accordance with 10 CFR 2.390 of the NRCs Rules 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).

If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Richard Skokowski at 630-829-9620 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

Cynthia D. Pederson, Director Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Enclosure: Byron Inspection/Activity Plan DISTRIBUTION See next page