IR 05000454/2008002
| ML081350248 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/14/2008 |
| From: | Richard Skokowski Region 3 Branch 3 |
| To: | Pardee C Exelon Generation Co |
| References | |
| IR-08-002 | |
| Download: ML081350248 (7) | |
Text
May 14, 2008
SUBJECT:
BYRON STATION, UNITS 1 AND 2 NRC INTEGRATED INSPECTION REPORT 05000454/2008002; 05000455/2008002
Dear Mr. Pardee:
On March 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Byron Station, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on April 11, 2008, with Mr. David Hoots and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, two NRC-identified findings of very low safety significance were identified. These findings involved violations of NRC requirements. In addition, two licensee-identified violations which were determined to be of very low safety significance are listed in this report. Because of their very low safety significance, and because the issues were entered into your corrective action program, the NRC is treating these issues as Non-Cited Violations in accordance with Section VI. A. 1 of the NRC Enforcement Policy.
If you contest the subject or severity of a Non-Cited Violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Byron Station. 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).
Sincerely,
/RA/
Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Enclosure:
Inspection Report 05000454/2008002; and 05000455/2008002 w/Attachment: Supplemental Information
cc w/encl:
Site Vice President - Byron Station
Plant Manager - Byron Station
Regulatory Assurance Manager - Byron Station
Chief Operating Officer and Senior Vice President
Senior Vice President - Midwest Operations
Senior Vice President - Operations Support
Vice President - Licensing and Regulatory Affairs
Director - Licensing and Regulatory Affairs
Manager Licensing - Braidwood, Byron, and LaSalle
Associate General Counsel
Document Control Desk - Licensing
Assistant Attorney General
Illinois Emergency Management Agency
J. Klinger, State Liaison Officer, State of Illinois
P. Schmidt, State Liaison Officer, State of Wisconsin
Chairman, Illinois Commerce Commission
B. Quigley, Byron Station
SUMMARY OF FINDINGS
...........................................................................................................1
REPORT DETAILS
.......................................................................................................................3 Summary of Plant Status...........................................................................................................3
REACTOR SAFETY
....................................................................................3
1R04 Equipment Alignment
................................................................3
1R05 Fire Protection
...........................................................................4
1R07 Annual Heat Sink Performance
.................................................5
1R11 Licensed Operator Requalification Program
.............................5
1R12 Maintenance Effectiveness
.......................................................6
1R18 Plant Modifications
....................................................................8
1R20 Outage Activities
.......................................................................9
1R22 Surveillance Testing
................................................................10
2. Radiation Protection..................................................................................12
2OS1 Access Control to Radiologically Significant Areas (71121.01).................12 2OS2 As-Low-As-Is-Reasonably-Achievable (ALARA) Planning And Controls (71121.02).................................................................................................17
4OA1 Performance Indicator Verification
...............................................19
4OA2 Identification and Resolution of Problems
....................................21
4OA5 Other Activities..........................................................................................25
4OA6 Management Meetings..............................................................................25
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
.....................................................................................................1
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED.........................................................1
LIST OF DOCUMENTS REVIEWED
.........................................................................................2