IR 05000454/2011005

Errata for Byron Station Units 1 and 2 Integrated Inspection Report 05000454-11-005; 05000455-11-005

ML12046A110
Person / Time
Site:	Byron
Issue date:	02/14/2012
From:	Eric Duncan Region 3 Branch 3
To:	Pacilio M Exelon Generation Co, Exelon Nuclear
References
IR-11-005
Download: ML12046A110 (7)

Text

ary 14, 2012

SUBJECT:

ERRATA FOR BYRON STATION, UNITS 1 AND 2, INTEGRATED INSPECTION REPORT 05000454/2011-005; 05000455/2011-005

Dear Mr. Pacilio:

On February 7, 2012, the U. S. Nuclear Regulatory Commission (NRC) issued an Integrated Inspection Report 05000454/2011-005, 05000455/2011-005 for your Byron Station. An inspection sample for the Mitigating Systems Performance Index Residual Heat Removal System was inadvertently omitted in the original report.

The enclosed errata contain the omitted inspection sample. No findings were identified. We regret any inconvenience this may cause.

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 NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning this errata, we will be pleased to discuss them with you.

Sincerely,

/RA/

Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66

Enclosure:

Errata for Inspection Report 05000454/2011-005; 05000455/2011-005

REGION III==

Docket Nos: 05000454; 05000455 License Nos: NPF-37; NPF-66 Report No: 05000454/2011005; 05000455/2011005 Licensee: Exelon Generation Company, LLC Facility: Byron Station, Units 1 and 2 Location: Byron, IL Dates: October 1, 2011, through December 31, 2011 Inspectors: B. Bartlett, Senior Resident Inspector J. Robbins, Resident Inspector R. Ng, Project Engineer J. Dalzell-Bishop, DRS Emergency Response Specialist J. Cassidy, Senior Health Physicist R. Jickling, Senior Emergency Preparedness Inspector B. Palagi, Senior Operations Engineer J. Nance, Reactor Engineer J. Benjamin, Braidwood Senior Resident Inspector C. Thompson, Resident Inspector, Illinois Emergency Management Agency Approved by: E. Duncan, Chief Branch 3 Division of Reactor Projects

4. OTHER ACTIVITIES (OA)

4OA1 Performance Indicator Verification (71151)

.1 Mitigating Systems Performance Index - Residual Heat Removal System a. Inspection Scope The inspectors sampled licensee submittals for the MSPI - Residual Heat Removal System PI for Unit 1 and Unit 2, for the period from October 1, 2010, through September 30, 2011. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6, dated October 2009, was used. The inspectors reviewed the licensees operator narrative logs, issue reports, event reports, MSPI derivation reports, and NRC Integrated Inspection Reports for the period of October 1, 2010, through September 30, 2011, to validate the accuracy of the submittals. The inspectors reviewed the MSPI component risk coefficient to determine if it had changed by more than 25 percent in value since the previous inspection, and if so, whether the change was in accordance with applicable NEI guidance. The inspectors also reviewed the licensees issue report database to determine if any problems had been identified with the PI data collected or transmitted for this indicator. Documents reviewed are listed in the Attachment to this report.

This inspection constituted two MSPI residual heat removal system samples as defined in IP 71151-05.

b. Findings No findings of significance were identified.

4OA6 Meetings

.1 Exit Meeting Summary On January 12, 2012, the inspectors presented the inspection results to Mr. B. Youman, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.

.2 Interim Exit Meetings Interim exits were conducted for:

• The results of an Operator Licensing inspection with the Lead Operations Training staff instructor, Mr. M. McCue, via telephone on December 8, 2011.

• The results of an annual review of Emergency Action Level and Emergency Plan changes with the Emergency Preparedness Coordinator, Mr. R. Kartheiser, via telephone on December 7, 2011.

• The results of Occupational and Public Radiation Safety programs inspections with the Site Vice President, Mr. T. Tulon, on November 10, 2011, and with the Acting Plant Manager, E. Hernandez, on December 28, 2011.

The licensee acknowledged the issues presented. The inspectors confirmed that none of the potential report input discussed was considered proprietary. Proprietary material received during the inspection was returned to the licensee.

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee T. Tulon, Site Vice President B. Youman, Plant Manager D. Coltman, Operations Manager J. Feimster, Design Engineering Manager D. Damptz, Acting Maintenance Director S. Swanson, Nuclear Oversight Manager B. Barton, Radiation Protection Manager K. Anderson, Acting Radiation Protection Manager A. Creamean, Chemistry Manager D. Gudger, Regulatory Assurance Manager T. Hulbert, Regulatory Assurance Specialist R. Cameron, Licensed Operator Requalification Lead Nuclear Regulatory Commission E. Duncan, Chief, Branch 3, Division of Reactor Projects LIST OF ITEMS OPENED, CLOSED AND DISCUSSED Open None Closed None

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 February 14, 2012 Mr. Michael